Annual Report of Institute of Atomic Energy 2007

Edited by China Institute of Atomic Energy

Atomic Energy Press

Beijing, China

图书在版编目（CIP）数据

中国原子能科学研究院年报. 2007：英文/《中国原 子能科学研究院年报》编辑部编.—北京：原子能出 版社，2008.6 ISBN 978-7-5022-4136-0

Ⅰ.中… Ⅱ.中… Ⅲ.核能－研究－中国－2007－年报－ 英文 Ⅳ.TL-54

中国版本图书馆 CIP 数据核字（2008）第 086051 号

Annual Report of China Institute of Atomic Energy 2007

Published by Atomic Energy Press, P. O. Box 2108, Postcode:100037, , China Printed by Printing House of WenLian in China Format: 880 mm×1 230 mm 1/16 First Edition in Beijing, June 2008 First Printing in Beijing, June 2008 ISBN 978-7-5022-4136-0

Annual Report of China Institute of Atomic Energy 2007 出版发行 原子能出版社（北京市海淀区阜成路 43 号 100037） 责任编辑 傅 真 王宝金 印 刷 中国文联印刷厂 经 销 全国新华书店 开 本 880 mm×1230 mm 1/16 字 数 533 千字 印 张 19.125 版 次 2008 年 6 月北京第 1 版 2008 年 6 月北京第 1 次印刷 书 号 ISBN 978-7-5022-4136-0 印 数 1-500 定 价： ¥100.00 元 版权所有 侵权必究 Editorial Committee of Annual Report of China Institute of Atomic Energy

Editor in Chief ZHAO Zhi-xiang Associate Editor in Chief XU Jin-cheng Consultant RUAN Ke-qiang WANG De-xi WANG Fang-ding WANG Nai- ZHANG Huan-qiao Editorial Committee CHEN Yong-shou CHEN Zhong-lin GU Zhong-mao JIANG Xing-dong LI Ji-gen LI Lai-xia LIN Can-sheng LIU Da-ming LIU Sen-lin LIU Wei-ping LU Zhong-cheng LUO Zhi-fu MA Zhong-yu SHAN Yu-sheng -kang SHU Wei-guo WAN Gang WANG Guo-bao WANG Jian-qing XIA Hai-hong XIAO -fu XU Mi XUE Xiao-gang YANG He-tao Guo-an YE Hong-sheng YIN Zhong-hong ZHANG Chang-ming ZHANG Jin-rong ZHANG Tian-jue ZHANG Wei-guo ZHAO Chong-de ZHOU Chang-chun ZHOU Shu-hua ZHU Sheng-yun

Editors HOU Cui-mei LI Xue-liang MA Ying-xia TANG Xiao-hao WANG Bao-jin WANG Tiao-xia ZHANG Xiu-ping

Address: P. O. Box 275-65, Beijing 102413, China Tel: 8610-69358024, 69357285 Fax: 8610-69357285 E-mail: [email protected] URL: http://ZYKB.chinajournal.net.cn

PREFACE 1

PREFACE

Under the leadership of high-level administrative organs related and the direct leadership of China National Nuclear Corporation (CNNC), all the staff in China Institute of Atomic Energy (CIAE) adhered to the work guidance “strengthening macro-control, grasping important work well, insisting that people are very important, promoting harmonious development” and worked hard together and completed all work tasks in 2007.

1 Mid- and Long-Term Planning of CIAE finalized Edition of Mid- and Long-term Planning of CIAE has been drawn up and finished through common efforts. The progress on the important part of general development and construction programs kept well. “The feedback about the results from new era consultation company” and starting-up projects advices in 2007 of general development and construction programs in 2007 have been submitted. National Laboratory of Sanqiang has entered into the first batch pilots of National Science and Technology Laboratory for National Defense and the preparatory work has been started. Origin drafts about National Development Planning of Fast Breeder Reactor and Mid- and Long- term Planning about Technology Research and Development of Fast Breeder Reactor have been compiled.

2 Actively pushing investment construction of fixed assets and promoting fundamental capabilities successively Adjusted general aims and budgetary estimates of China Experimental Fast Reactor have jointly been approved by the Ministry of Science and Technology of the People’s Republic of China and Commission of Science Technology and Industry for National Defense. Two important milestones of in-reactor component installment and main control room adjustments have been realized smoothly. All sub-items buildings of China Advanced Research Reactor on-site have been completed and the installation of all the equipments has been finished. New in-reach reports about HI-13 Tandem Accelerator Upgrading project has been submitted to the Commission of Science, Technology and Industry for National Defense and waited for approval. For 100 MeV cyclotron, Part construction design and a serial key component manufactures of magnetic pole of main magnet, etc have been finished. Bidding for the building of radiochemical laboratory of nuclear fuel reprocessing has been finished, the compilation and appraisal about environment evaluation and security analysis reports and occupa-

PREFACE 2

tional disease prevention have been completed; evaluation for qualified providers of main equipment manufactures and the preparatory work for biding of installation have been done. Annual planning for Decommissioning of nuclear facilities and special project of radioactive waste treatment has been achieved basically. Newly decommissioning projects have been submitted. Important assessment projects in 2007 have been completely well. Key laboratory of nuclear data measurement and evaluation technology has come into building completion and passed checkup; installation and adjustment of experimental platform and surveillance system and impulsion upgrading of accelerator in key lab of dose and calibration technology of science and technology for national defense have been finished. Hot cell 303 and critical device have finished annual aims and are being submitted; construction projects of dose science and research conditions have been authorized. Checkup and acceptance for the construction project of Sino-American nuclear materials management technology have been completed. Hardware platform construction of demonstration project for science and technology management information system has been finished. Investment projects of newly added fix assets have gradually been started up.

3 Science and research production tasks completed entirely and a batch of new projects authorized Fundamental projects for national defense are in good progress and have reached phase aims and have passed mid-term summings-up appraisal organized by CNNC. Five projects of 16 in-research projects based on technology have finished checkup and acceptance. In-research projects in the field of nuclear energy development went on smoothly. A group of important achievements, such as science research of adjustment phase of reprocessing treatment pilot plant, isotopes and radiation technology application and so on, have gotten important results. Science and research projects about three wastes are in process on schedule. Special project for technology research on geological disposal of high-level radioactive wastes has got approval. The operations of large facilities are in good condition. Heavy Water Research Reactor has operated for 2 256 hours; Light Water Research Reactor has operated for 2 704 hours; hot cell truck operation of cement solidification production line in the facility of comprehensive disposal workshop of radioactive waste liquids has been conducted; low-level waste liquids disposal workshop has operated for 12 days safely. Research fields of science research projects have been expanded and new channels for applying outlays have been opened up. The scheme and application of Science and research of landscape orientation and the 11th Five Years Plan have been strengthened.

PREFACE 3

12 awards have been conferred by Commission of Science, Technology and Industry for National Defense and 17 awards have been conferred by CNNC. 350 GF reports have been submitted and 69 patents have been applied. Strategic cooperation agreements with 404 and 202 under the CNNC and high energy physics of Chinese Academy of Science and some universities have been signed; in 2007, many important activities have been held including experience exchanges about being built projects of nuclear power in CNNC, and some others.

4 Stable development of nuclear technology industry, engineering technology service in good condition Distribution incomes reached to 220 million and profits were 2.05 million in Beijing Atom Hightech Co., Ltd. and management index has been completed. Research and development of important projects including 10 MeV/15 kW high power electronic radiation accelerator system, 4-6 MeV adjustable and no defect-detection electronic linac, EDS-M explosive monitoring devices, mobile container inspection system carried by truck, radioactive matter inspection system and so on. Key projects of advanced radioactive trace technology development in petroleum industry has been approved, and gotten the special project support of Commission of Science, Technology and Industry for National Defense. In the respect of nuclear engineering service, the decommissioning of cobalt source of biological physics institute of Chinese Academy of Science has been finished, and the building scheme about decommissioning engineering of radioactive waste and old source storage in Jilin Province has passed appraisal. For nuclear power technology service, 15 contracts have been sighed and contract sum has reached to 16.817 7 million and 15 contracts related to starting-up of Qinshan phase Ⅱ have been signed; for foreign engineering projects, hot cell construction scheme and budgets assessment of Qiaqima nuclear power plant in Pakistan have been submitted, some projects are being under discussion such as constructing sub-critical devices, research reactor, etc. Industry fund of CIAE, which has been approved totals to 1.43 million.

5 Reform work deepened, management and supervision strengthened Management system of graduate school has been adjusted, and reform and adjustment of electronic instrument plant have been completed. Investigation and research and consulting and measurement for the staff related to coming into marketing of Beijing Atom Hightech Co., Ltd. have been conducted. Some regulations about distribution rules reform, outlay budget, laws, quality and so on have been released; law consciousness has been improved. Salary reform went on well, average incomes have been increased.

PREFACE 4

Engineering projects management has been strengthened and parts of checkup and acceptance projects shifted to fixed assets have been completed. The auditing of economic responsibility for acting president has been completed by CNNN, and the auditing of fiscal final accounting in 2006 has been conducted. Quality management system reappraisal has been passed by authentication center. No quality accidents happened, and annual quality aims have been achieved. Workshop on efficiency and capacity supervision has been held, 33 themes has been approved.

6 Talent infrastructure kept reasonable, talents team construction remarkable 126 persons recruited to CIAE, including 7 doctor’ degree holder, 81 master’s degree’ holder. New comers included 44 students for doctor’s degree and 59 students for master’s degree; 20 persons got doctor’s degree and 83 people got master’s degree. 4 persons got government special subsidies. One person got the title “middle age and youth experts making remarkable contribution”, staff training temporary method of CIAE has been established. The first run of report meeting of investigation and research for new staff was held. 2nd batch of young academic leaders finished training. The proportion of advanced technician to common technician reached to 9.5%; 21 persons have passed occupation qualification identification.

7 Security system operated efficiently No accidents took place, and demonstration on anti-terrorism and emergent accident response has been held.

Professor Editor in chief President, CIAE

June, 2008

CONTENTS I

CONTENTS

IMPORTANT NUCLEAR SCIENCE ENGINEERING

China Experimental Fast Reactor (CEFR) General Technology Outline Consideration of China Demonstration Fast Reactor·······YANG Hong-yi, et al(3) Progress of the Generation Ⅳ International Forum (GIF)······································YANG Hong-yi, et al(5) Preliminary Calculation and Analysis of China Demonstration Fast Reactor Core Physics ······················ ·····································································································································LI Ze-hua, et al(7) Consideration for Thermal-Hydraulics Limiting Design Parameters of SFR Plant ··············LIU Yi-zhe，et al(7) Reliability Analysis of Cooling Water System of CEFR Based on GO Methodology·····YANG Li-fang, et al(8) Development of V2MB Used to Linearized Stress Results From ANSYS ·······················WEN Jing, et al(9) Preliminary Analysis of Thorium Utilization Features in FBR ·······································GANG Zhi, et al(9) Preliminary Strategy Study on Thorium Utilization Based on FBR ························ZHAO Jin-kun, et al(10) Analysis of Measurement Data for Neutron Counting Assembly on Reactor···········ZHAO Yu-sen, et al(11) Preparatory Calculation of Noise Analysis on CEFR·············································FAN Zhen-dong, et al(12) Treating Experimental Data of Inverse Kinetic Method·······································CHEN Xiao-liang, et al(13) Development on Reaction Rate Relative Distribution for Experimental Data Processing Program·········· ···························································································································WANG Da-fei, et al(14) Analytical Method for Determinating Carbon Impurity in Sodium·································XIE Chun, et al(15) Calibration of China Hydrogen Meter in Argon················································HONG Shun-zhang, et al(15) China Advanced Research Reactor (CARR) Piping Stress Analysis of Coolant Purification System in China Advanced Research Reactor·················· ··························································································································DAI Shou-tong, et al(18) Piping Stress Analysis of Heavy Water Purification System in China Advanced Research Reactor········· ··························································································································DAI Shou-tong, et al(19) Piping Stress Analysis Optimizing of Secondary Cooling Water System in China Advanced Research Reactor······ ··························································································································DAI Shou-tong, et al(20) Piping Stress Integrative Analysis of Reactor Cooling water System and Secondary Cooling Water System in China Advanced Research Reactor······························································DAI Shou-tong, et al(20) Technical Study on Radioisotopes Production of CARR···················································DING Li, et al(21) Beijing Radioactive Ion-Beam Facility Progress on Design and Construction of CYCIAE-100·············································································· ······················································Technology Division of Beijing Radioactive Ion-Beam Facility(22) Design and Construction Progress of Main Magnet for CYCIAE-100················ZHANG Tian-jue, et al(26) Test Stand Commissioning for CYCIAE-100····························································································· ·····················································Technology Division of Beijing Radioactive Ion-Beam Facility (30) Analytical Calculations of Chopper for CRM Cyclotron··········································AN Shi-zhong, et al(32) Study of Stripping Efficiency for CYCIAE-100························································AN Shi-zhong, et al(34) Study of Extracted Beam Dispersion for CYCIAE-100············································AN Shi-zhong, et al(36) II Annual Report of China Institute of Atomic Energy 2007

Radiation Field Calculation of CYCIAE-100·································································BI Yuan-jie, et al(38) Study on Space Charge Effect in Isochronous Cyclotron···············································BI Yuan-jie, et al(41) Magnetic Measurement for 15-20 mA Ion Source·························································JIA Xian-lu, et al(43) Design of 15-20 mA H－ Cusp Source···········································································JIA Xian-lu, et al(45) Three Methods and Comparison for Vertical Acceptance Calculation of CYCIAE-100··························· ························································································································YAO Hong-juan, et al(48) Analytical Calculation for Fringe Field of Spiral Inflector····································YAO Hong-juan, et al(51) Influence of Radial Field on Emittance in Median Plane at CYCIAE-100·········ZHONG Jun-qing, et al(53) Influence of Non-uniform Conductance of Main Magnet on Median Plane Field in CYCIAE-100·········· ······················································································································ZHONG Jun-qing, et al(56) Test and Analysis on Multipactoring Phenomenon in 70 MHz RF System of CRM Cyclotron················· ·······································································································································XIA Le, et al(59) PFD Design and Simulation Based on FPGA······························································YIN Zhi-guo, et al(62) Power Loss on Cavity of CYCIAE-100··················································································JI Bin, et al(64) Vertical Focusing Enhancement Through Asymmetric Shimming Method for CYCIAE-100··················· ···························································································································WANG Chuan, et al(65) Cryopumping System Design for CYCIAE-100·······················································PAN Gao-feng, et al(67) Control System Development for CRM Cyclotron··················································HOU Shi-gang, et al(69) Beam Line Design and Construction of Gas Target for a Medical Cyclotron CYCIAE-30······················· ······························································································································WEI Su-min, et al(70) Water-Cooling System Design of Dee for RF System of CYCIAE-100······················WEI Su-min, et al(72) Design of Emittance Scanner for Intense Low-Energy H－ Beam························SONG Guo-fang, et al(74) Progress Report of Beijing Radioactive Ion-Beam Facilities (BRIF) in 2007········CAO Xiao-ping, et al(76) Progress of Superconducting Booster of BRIF Project in 2007·······························ZHOU Li-peng, et al(77) Current Status of Isotope Separator On-Line of BRIF Project (BRIF-ISOL) ············CUI Bao-qun, et al(78)

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH

Nuclear Physics Tetrahedral Symmetry in Superheavy Nuclei·····················································CHEN Yong-shou, et al(81) Microscopic Optical Potentials of Nucleon-Nucleus and Nucleus-Nucleus Scattering····························· ···························································································································MA Zhong-yu, et al(83) Inner Crust of Neutron Stars in Relativistic Mean Field Approach···························CAO Ji-guang, et al(83) Relativistic Quasiparticle Random Phase Approximation With a Separable Pairing Force······················· ································································································································TIAN Yuan, et al(85) Effect of Tensor Interaction on Spin-Orbit Splitting·························································ZOU Wei, et al(85) Probing Density Dependence of Symmetry Energy With Heavy Ion Collisions··ZHANG Ying-xun, et al(87) Exploring Symmetry Energy With Emitted and Using Quantum Molecular Dynamics Model··········································································································ZHANG Ying-xun, et al(88) Analysis of Intermediate Energy -Induced Spallation Reactions by Improved Quantum Molecular Dynamics Plus Statistical Decay Model·········································································OU Li, et al(89) Modified Woods-Saxon Potential for Heavy-Ion Fusion Reaction··························TIAN Jun-long, et al(90) CONTENTS III

Specific Heat in Hadron and Quark-Gluon Matters······················································SA Ben-hao, et al(90)

Direct Photon Production in p+p and Au+Au Collisions at SNN =200 GeV in PACIAE························ Model···················································································································LI Xiao-mei, et al(91) Rotational Structures at Ultrahigh Spin in 157, 158, 159Er··········································DONG Bao-guo, et al(91) Theoretical Models of Cell Inactivation by Ionizing Particles·····························CAO Tian-guang, et al(92) Monte-Carlo Simulation of Cellular S Value and Specific Energy for Electrons···GENG Jin-peng, et al(93) Study on High-Spin State and Signature Inversion in 110Ag············································HAO Xin, et al(94) Systematics of Shears Mechanism in A~110 Mass Region······································HE Chuang-ye, et al(95) Study of Structure of High-Spin States in 112In·······························································LI Xue-qin, et al(97) Triaxial Shape in 129Ce·······································································································LIU Ying, et al(98) Dose Rate Effect on DNA Damage Induced by Heavy Ion····································KONG Fu-quan, et al(99) DNA Concentration Effect on DNA Radiation Damage Induced by 7Li Ion and γ-ray····························· ·······················································································································KONG Fu-quan, et al(101) Investigation of Dose Effect of DNA Strand Breaks Damage Induced by Protons·············SUI Li, et al(102) Measurement Techniques for Low-Intensity Beam on HI-13 Tandem Accelerator·····GUO Gang, et al(103) Scheme of Long-Distance Control for RS232 Serial Devices With New Beam-Line in Experimental Hall of HI-13 Tandem Accelerator············································································SHI Shu-ting, et al(104) Etching Technique of Solid Nuclear Tracks Detector for Heavy-Ion Micro-beam Diagnostics················ ·································································································································HUI Ning, et al(106) T1 Chamber in Heavy Ion Radiation Facility·····································································CHEN Quan(107) Design of SRAM Testing System Based on Virtual Instrument Technology················TENG Rui, et al(108) Experimental Study of Neutron-Neutron Quasi-Free Scattering and Neutron-Neutron Final-State Interaction······································································································RUAN Xi-chao, et al(109) Neutron Emission Double-Differential Cross-Section (DDX) Measurement of Natural Iron at 8.17 MeV Neutrons·········································································································RUAN Xi-chao, et al(109) Double-Differential Cross-Section Measurement of 9Be(n, xα) Reaction Induced by 14.8 MeV Neutrons ·······················································································································RUAN Xi-chao, et al(110) A Beam-Monitoring Time of Flight System With Plastic Scintillator··························QIN Xing, et al(110) 13N+p Elastic Resonance Scattering via Thick-Target Method····························WANG You-bao, et al(112) Levels in 13N Examined by 12C+p Resonance Elastic Scattering via Thick Target Method······················· ·································································································································QIN Xing, et al(113) Production of 22Na Secondary Beam·········································································JIANG Chao, et al(114) Production of 6He Secondary Beam With High Purity···················································-ju, et al(115) Measurement of Angular Distribution for 8Li (p, d)7Li Reaction···································LI Yun-ju, et al(117) 12 11 ， γ-ray Spectroscopy of Λ C and ΛB······································································FU Yuan-yong et al(118) A Method of Evaluating Discrepant Data························································HUANG Xiao-long, et al(119) Theoretical Analysis of n+6Li Reactions and Establishment of Neutron Data Libraries at Incident Neutron Energy Below 20 MeV····················································································WANG Ji-min, et al(119) Establishment of Double Differential Cross Section File for 10B at Incident Neutron Energy Below 20 MeV··················································································································WANG Ji-min, et al(120) Establishment of Double Differential Cross Section File for 11B at Incident Neutron Energy Below 20 MeV·················································································································WANG Ji-min, et al(120) 5He Emission in Neutron Induced 11B Reactions····················································WANG Ji-min, et al(121) IV Annual Report of China Institute of Atomic Energy 2007

Theoretical Calculation of n+28Si Reaction Below 20 MeV··············································ZHANG Hua(121) Benchmarks for 28Si Evaluation Data of CENDL-3.1·······················································ZHANG Hua(123) Benchmark Testing for 14N Evaluation of CENDL-3.1··········································WU Hai-cheng, et al(124) Benchmark Testing for Silicon Evaluation of CENDL-3.1····································WU Hai-cheng, et al(125) Benchmark Testing for 16O Evaluation of CENDL-3.1··········································WU Hai-cheng, et al(127) Application of TALYS Code in Study of Mass Distributions of Fission Fragment···································· ·····················································································································CHEN Yong-jing, et al(128) Research on Prompt Neutron Multiplicity Distribution of Fission Fragment····CHEN Yong-jing, et al(128) Introduction and Application of TALYS Code·································································TAO Xi, et al(129) Calculation of Neutron-Induced Reaction on 181Ta Below 30 MeV·································TAO Xi, et al(129) Theoretical Model Calculations of n+58, 60, 61, 62, 64Ni With EMPIRE Code··················QIAN Jing, et al(129) Exploitation of Nuclear Reaction Model Code EMPIRE-2.19·····································QIAN Jing, et al(130) Development of a Thickness Measurement Set Using α Energy Loss······················DU Ying-hui, et al(130) Design and Debug of a New Foil Stretcher for Plunger Targets································FAN Qi-wen, et al(131) Progress of Neutron Residual Stress Instrument Project at CARR·····························-hong, et al(133) Diffraction Measurements of Residual Stress in High Tension Steel by Neutron······LI Jun-hong, et al(134) Progress in High Resolution Powder Diffractometer at CARR··································LI Mei-juan, et al(134) Repair and Mend of Controlling System of Neutron Residual Stress Diffractometer································ ·······················································································································YU Zhou-xiang, et al(135) Monte-Carlo Simulation for Neutron Monochromator Shielding·······················JIAO Xue-sheng, et al(136) Simulation and Optimization on Polarized Neutron Reflectometry······················LIU Rong-deng, et al(136)

Study on Thermal Expansion Property of Molybdates Er1.6Cr0.4Mo3O12··················WU Mei-mei, et al(137)

Preparation and Related Measurements of Silicides of Rare Earth Metals R5Si3 (R=Pr, Nd, Tb, Dy, Ho, Er) Compounds···············································································································ZU Yong, et al(137) Relocation of Neutron Instruments From Juelich Research Center in Germany···TIAN Geng-fang, et al(138) Progress of Simultaneous Measurement Method·····················································DOU Yu-ling, et al(138) AMS Measurement of “In-Situ Produced Cosmogenic” 10Be in Loess Quartz From Luochuan··············· ···························································································································DOU Yu-ling, et al(139) Application of Bragg Curve Detector for Heavy Nuclear Measurements in AMS·······LI Chao-li, et al(140) Preliminary Research on Measurement of 126Sn by AMS····································SHEN Hong-tao, et al(142) Method of 236U Measurement With AMS and Its Applications························WANG Xiang-gao, et al(142) An Ultra-sensitive Method for Quantization of 79Se to Be Used as Environmental and Biological Tracer Isotope via Accelerator Mass Spectrometry························································WANG Wei, et al(144) High Efficiency 41Ca Measurements With AMS·······················································WU Shao-lei, et al(148)

Prepare of HfF4 Samples for AMS Measurement by Solid-Phase Reaction Method····TUO Fei, et al(149) Improvement of AMS Measurement of 182Hf···································································TUO Fei, et al(150) Study on Reflection of Infrared Light Through Polyester Films Modified by Nuclear Pores·················· ························································································································LIU Cun-xiong, et al(150) Preliminary Study on a New Generation Natural Matrix Reference Material Suitable for Microanalysis ··················································································································HUANG Dong-hui, et al(152) Preliminary Study on Sampling Behavior of Multielements in NIST RM 2703 and SRM 2702 by Using Neutron Activation Analysis····················· ··············································HUANG Dong-hui, et al(153) Performance Improvement on CIAE Neutron Dosimetry Bubble Detectors····ZHANG Gui-ying, et al(155) Study on Stability of Personal Neuron Dosimetry-Bubble Detectors···············ZHANG Gui-ying, et al(157) Development of α Grid Ionization Chamber···········································································YANG Lu(158) CONTENTS V

Photoelectric Detector of GaAs Compound Semiconductor·································DING Hong-lin, et al(159) Development of Large Area CdZnTe Detector for Satellite Detection of X- and γ-ray····························· ·······················································································································DING Hong-lin, et al(160) High Power Laser and Accelerator Laser Induced Damage Threshold of Dielectric Coatings for Improving of Heaven-I System·················· ·························································································································GAO Zhi-xing, et al(161) Preliminary Study of Single-Shot SHG-FROG Measurement of Femtosecond Laser Pulses···················· ·······················································································································XU Yong-sheng, et al(161) Experimental Study of Interaction for Ultra-short Pulse Laser With Solid Plasmas·······LI Ye-jun, et al(162) Experimental Study of Effect for Hot Electron Producing With Various Laser Wavelength····················· ·································································································································LI Ye-jun, et al(162) Experimental Results of Target Velocities Detected by Side-On Shadowgraph System···························· ··························································································································GAO Shuang, et al(164) Titanium Film Protection and Uniformity of Beam································································LI Jin-hai (166) Design of Radiation Shield for 2 MeV Accelerator························································LI Jin-hai, et al(166) Performance of Beijing Pulsed Variable-Energy Positron Beam·······························MA Yan-yun, et al(167) Work Statement for Accelerating Tube With High Capture Efficiency·····················MA Yan-yun, et al(167) Science and Technology of Reactor Calculation Research for Bubble Effect Experiment of Uranium Solution············LIU Hong-wei, et al(168) Assessment of Critical Flow Model in RELAP5·················································CHEN Yu-zhou, et al(168) Function Qualification Tests of Specified Pressure Difference Check Valve···ZHANG Xue-feng, et al(168) Numerical Study on Thermal-Hydraulics Characteristics in In-Hospital Neutron Irradiator····················· ··························································································································MAO Yu-long, et al(170) Preliminary Design of Lead-Bismuth Eutectic Thermal-Hydraulic and Corrosion Test Loop··················· ······························································································································QIAN Yan-yue (171) Effect of SiC Nanowires on Flexural Properties of CVI-SiC/SiC Composites···········YANG Wen, et al(171) Effects of Heat Treatment on Microstructure and Flexural Properties of CVI-Tyranno-SA/SiC Composite ·····························································································································YANG Wen, et al(172) Effects of Interlayer and Matrix on Properties of Advanced CVI-SiC/SiC Composites···························· ·····························································································································YANG Wen, et al(173)

Progress of Advanced UO2 Fuel Pellets Irradiation Program········································XU Xi-an, et al(174) Microstructural Analysis on JLF-1 Steel Tested by Fatigue Deformation····················LI Huai-lin, et al(175) Cyclic Softening Effect on Design Margin of JLF-1 Steel···········································LI Huai-lin, et al(176) Radiochemistry and Nuclear Chemistry Reaction Kinetics of Dihydroxyurea With Nitrous Acid and Its Effect on Stabilizing Pu(Ⅲ) ················· ························································································································YAN Tai-hong, et al(178) Pu(Ⅳ ) Reduction and U/Pu Split in Purex Process by Dihydroxyurea ·················YAN Tai-hong, et al(178) Formic Denitration for Recovery of Plutonium ·································································HE Hui, et al(179) Oxidation of Pu(Ⅲ) With Liquid Tetroxide-Dinitrogen···········································LI Gao-liang, et al(179) Interfacial Reactive Kinetics of Back-Extraction of Np(Ⅳ) From 30%TBP-OK With Acetohydraxamic Acid·······················································································································ZUO Chen, et al(180) Electrochemical Behavior of Np(Ⅵ)/Np(Ⅴ) Ions in Nitric Acid Solutions at Platinum Electrode··········· ···························································································································· ZHANG Hu, et al(180) Computer Simulation of Co-decontamination Process in Purex········································HE Hui, et al(181) VI Annual Report of China Institute of Atomic Energy 2007

Radiolysis Stability of Hydroxyurea···········································································XIAN Liang, et al(181) Electrooxidation of Pu(Ⅲ) in 1BP Solution·······························································ZHANG Hu, et al(181) γ-Radiolysis of N, N-dimethylhydroxylamine and Methylhydrazine···························CHEN Hui, et al(182) Analysis of N, N-dimethylhydroxylamine by Gas Chromatography·························LI Gao-liang, et al(183) Application of Treating Organic Waste From Purex Process Using Supercritical Water Oxidation·········· ··························································································································WANG Liang, et al(184) Development of Big Flow Ratio Micro-mixer-settler Extractor··················CHANG Shang-wen, et al(184) Flow Measurement and Feedback Controlling in Bench Test Equipment··············GUO Jian-hua, et al(185) Research Progress in Pulsed Extraction Column························································ZHANG Bai-qing(186) Adsorption of Se, Zr and Pd by Glass, Quartz and Polyethylene at Trace Level···LIANG Xiao-hu, et al(186) Measurement of 90Sr in Soil Samples With Pure Instrumental Method···············SUN Hong-qing, et al(187) Influence of Pulse Plating Parameters on Electrodeposition of Uranium·······················-li(188) Study on Measurement of 93Zr················································································YANG Jin-ling, et al(190) Spectrophotometric Determination of Lanthanides in Solution·························WANG Xiu-feng, et al(190) Production and Separation of 101Tc········································································YOU Xin-feng, et al(191) Separation and Purification of Plutonium From High-Level Liquid Waste···········ZHAO Ya-ping, et al(193) Spectrophotometric Determination for Measuring Micro Th in Liquid Solution···YANG Jin-ling, et al(194) Measurement of Gamma Ray Emission Probability of 173Lu and 174Lu··············SUN Hong-qing, et al(194) Comparison of Detection Efficiency for Four Gamma Ray Detectors···························MA Peng, et al(195) Correction Method of Deviation in EDXRF····················································ZHENG Wei-ming, et al(196) Determination of Micro Silver in Plutonium Product···········································LIU Huan-liang, et al(197) Matrix’s Influence by HOPG Pre-diffraction EDXRF·················································SONG You, et al(198) Determination of Nitrite in Nitric Acid Medium by Fluoremetry··································SU Yu-lan, et al(199) Determination of Ag in Technique Process Research·························································SU Tao, et al(200) Determination of Alpha Activity in Organic Samples With Activity············LIANG Liang, et al(200) Determination of Anions in Ammonium Biuranate by Ion Chromatograph··········DENG Wei-qin, et al(201) Determination of Mo, Fe, Th, Ti in Uranium Compound by ICP-AES·························SU Yu-lan, et al(201) Development of On-Line Micro-analyzer for Hydrogen Fluoride in Uranium Hexafluoride···················· ·····························································································································FAN De-jun, et al(203) Development on Special Analytical System for Determination of Free Acid·······ZHANG Li-hua, et al(203) Primary Study on Pretreatment Technology for Analysis of High-Level Radioactive Samples················ ·························································································································SHENG Feng, et al(204) Brief Report of Uranium Compound Proficiency Test by Chemical Analysis and Test Center of CIAE··· ·························································································································LIU Quan-wei, et al(204) Effect of Various Matrix on Measurement of Isotopic Ratio of Trace Plutonium by MC-ICP-MS··········· ·····································································································································-li, et al(205) Measurement of Isotopic Ratio of Trace Plutonium by MC-ICP-MS With Dynamic Mode····················· ·······················································································································ZHANG Ji-long, et al(206) Determination of Plutonium in Environmental Samples by ID-MC-ICPMS·········ZHU Liu-chao, et al(207) Inter Comparison on Isotopic Abundance Measurement of Neodymium···········JIANG Xiao-yan, et al(207) Calculation of Full Energy Peak Efficiency and Coincidence-Summing Correction Using Monte-Carlo Method for Measuring Disk Source by HPGe γ-Spectrometry····························LI Jian-hua, et al(208) Radioactive Waste Treatment and Disposal Characterization of Polar Component of Adsorption Energy by Inverse Chromatography······················· CONTENTS VII

···················································································································ZHANG Zhen-tao, et al(209) Measurement of Fissure Surface Area Inside Glass Block by Inverse Chromatography·························· ···················································································································ZHANG Zhen-tao, et al(209) Determination of Optimum Parameters of Inverse Gas Chromatography········ZHANG Zhen-tao, et al(211) Solubility of Technetium (Ⅳ) in Beishan Groundwater················································WANG Bo, et al(211) Research on Diffusion of 99Tc in Bentonite···························································SONG Zhi-xin, et al(212) Calculation on Distribution of Americium Species in Beishan Groundwater·····GUAN Hong-zhi, et al(212) Influence of Waste Glass Composition on Solubility of Sulfate During Vitrification of HLW················· ·······························································································································LIU Li-jun, et al(213) Fabrication of Glass-Ceramic for Immobilization of ················ZHANG Zhen-tao, et al(214) Design of High Frequency Induction Power of Cold Crucible Melter System··········XU Jian-hua, et al(215) Determination of Designing Parameter of Cold Crucible···································QIE Dong-sheng, et al(216) Radioactive Liquid Wastes Integrated Treatment Facility Went Into Work in State······YAN Xiao, et al(217) Isotopes Synthesis of Intermediates of 3, 4, 3-LI-(1, 2-HOPO) for Decorporating Plutonium································· ·······················································································································SHEN Lang-tao, et al(218) Design of Heat Fuel Core of 238Pu Radioisotope Thermoelectric Generator··············LUO Zhi-fu, et al(218) Design of Heat Source Capsule for 3 W Radioisotope Thermoelectric Generator·····LUO Zhi-fu, et al(219) Investigation on Effects of Neutron Irradiation on Tantalum······································LUO Zhi-fu, et al(219) 177Lu Labeled Radiopharmaceuticals for Cancer Therapy··········································LUO Zhi-fu, et al(220) Research Progress of 124Xe Gas Target System for High Purity 123I Preparation········LUO Zhi-fu, et al(220) Application of Automatic Control System in 123I Production by 124Xe Gas-Target····ZHANG Bao-qi, et al(221) Preparation of 125I Ladled Microspheres··························································ZHAO Ming-qiang, et al(222) Preparation of Monoclonal Antibody Against CA125 and It’s Applications in Immunoassay·················· ······················································································································FENG Shu-yuan, et al(222) Development of Surface Plasmon Resonance Based Biosensor Immunoassay for sulfadiazine··············· ································································································································LI Zi-ying, et al(223) Synthesis and Preliminary Evaluation of Novel Iodinated Sigma2 Receptor Ligand································ ···························································································································FAN Cai-yun, et al(223) Applied Mathematics and Computer Technology Application of Monte-Carlo Method in Monochromator Radiation Protection··················LIU Bao-jie(224) Monte-Carlo Calculations of Detection Efficiency and Coincidence Summing Correction for HPGe γ Spectrum Instrument····························································································FENG Shu-qiang(224) Effects of Accelerating Growth on Evolution of Large Harmonious Unifying Network Model··············· ····································································································································LI Yong, et al(225) Small World Effect for HUHPM: Short APL·························································FANG Jin-qing, et al(227) Toward a Harmonious Unifying Hybrid Model for any Evolving Complex Networks····························· ························································································································FANG Jin-qing, et al(228) Synchronization Control of Periodic State in BTN With SW Topology·····················,et al(230) Nuclear Safeguards Techniques Detecting Technique for Characteristic Electromagnetic Signal of Uranium Centrifuge Enrichment Plant ·························································································································LIU Guo-rong, et al(232) Experiment for Measurement of Uranium Enrichment With Small-Size CZT Detector···························· ··························································································································LIU Hong-bin, et al(232) VIII Annual Report of China Institute of Atomic Energy 2007

Development of Portable Handheld Neutron Counter············································MENG Yan-tai, et al(233) Scheme Design of Combined Fuel Assembly Measurement Device·······················LIU Hong-bin, et al(233) Establishment and Development of CAEA-IAEA Joint Training Center on Nuclear Safeguards and Security·························································································································SHEN Ning(234) Development of α-Waste Measurement Equipment for 200 L Drum·························ZHU Li-qun, et al(235) Radiation Protection and Environmental Protection Simulation of Concentration Distribution of 3H in CIAE Groundwater····················CHEN Chao, et al(236) Theoretical Calculation of Monoenergetic Electron Induced DNA Early Damage With Track Structure Method···················································································································YUE Feng, et al(237) Comparative Test of Glass Badge and OSL.TLD····················································XIAO Xue-fu, et al(238) Characterization Survey During Decommissioning·························································WEN Fu-ping(239)

IMPORTANT NUCLEAR INSTALLATION AND EQUIPMENT

Annual Report of HWRR in 2007·········································································ZHANG Xing-wang(243) MNSR Annual Operation Report··················································································ZHU Guo-sheng(245) HI-13 Tandem Accelerator in 2007········································································KAN Chao-xin, et al(246)

APPENDIX

International Scientific Technology Exchanges in 2007········································································(249) CIAE Seminars in 2007·····················································································································(257) Subject of Prize of Science, Technology and Industry for National Defense···························(260) CIAE Application of Patent in 2007·································································································(261) List of Scientific Publication in Foreign Languages in 2007······················································(266) List of Scientific Publication in Chinese in 2007·················································································(272) List of Lectures in International Meetings in 2007·················································································(285)

IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Experimental Fast Reactor 3

China Experimental Fast Reactor (CEFR)

General Technology Outline Consideration of China Demonstration Fast Reactor

YANG Hong-yi, ZHOU Pei-de, YU Hong, TIAN He-chun, LI Ze-hua, XIE Guang-shan, TIAN Chuan-jiu, LIU Yi-zhe

For developing the demonstration fast reactor, “We are Primary and collaborate with foreign countries”, this direction principle has been adopted to design and construct the China Demonstration Fast Reactor (CDFR). We have carried on the technology preparation work and described the general technology outline for CDFR.

1 Main technology target According to the purpose of CDFR and China fast reactor development program, the main technol- ogy targets of CDFR are showed here. 1) Comply with the safety and reliability equipments of GIV System. 2) Potentially economical. 3) Comply with the sustainable development of nuclear energy technology. 4) Validated technology is adopted to reduce the risk. 5) Comply with the standardization and industrialization. 6) General parameters reach the level of commercial nuclear power plant.

2 Main technology outline The CDFR is characterized by a pool type structure for the primary circuit, with 2 100 MW thermal power and 870 MW electric power. The loading of the reactor will be the MOX fuel. Sodium, sodium and water steam as heat transfer medium successively for the three circuits of the main heat transfer system. The main parameters are showed in Table 1. The CDFR core layout is showed in Fig.1. The main heat transports systems are showed in Fig.2. The primary circuit consists of three primary pumps and six intermediate heat exchangers. There are two secondary sodium circuits and two tertiary water-steam circuits, but only one turbo-generator. Each steam generator has ten modules. The secondary sodium is heated in the tube side of the intermediate heat exchangers, then it is passed to the superheaters and then to the evaporators. The superheated steam flows into main steam pipe and then drive the turbine generator.

3 Main technology features The main technology features of CDFR are considered as following. 1) The primary circuit is under ordinary pressure. 2) The CDFR is characterized by a pool type structure for the primary circuit. The main vessel has high capacity for heat storage. This kind of design ensures operators have enough time to analyze accidents and implement some methods. 3) The core thermal-hydraulic design ensures there are abundant values. 4 Annual Report of China Institute of Atomic Energy 2007

4) Hydraulic suspended rods are adopted as passive emergency protection shutdown system.

Table 1 Main parameters of CDFR

Parameters Value Parameters Value

Thermal power 2 100 MWt No. of stainless steel reflector rods 178

Electric power 870 MWe Storage position for spent fuel subassembly 188

Thermal efficiency 41.4% Primary coolant temperature Hot leg 354 ℃

Load factor 80% Cold leg 547 ℃

Plant life 40 Years Primary coolant flow rate 8 700 kg/s

Drive fuel charge MOX No. of coolant loops Primary 3

Coolant Sodium Secondary 3

Primary circuit configuration Pool No. of pump per loop in primary circuit 1

Average target of burn-up 66 MW·d/kg No. of pump per loop in secondary circuit 1

Maximum target of burn-up 100 MW·d/kg No. of IHX per loop 2

Breeding Ratio 1.0-1.3 No. of steam generator modules per loop 10

No. of fuel subassembly Inner zone 211 Secondary coolant temperature Hot leg 309 ℃

Middle zone 156 Cold leg 505 ℃

Outer zone 198 Secondary coolant flow rate 8 400 kg/s

No. of DHRS 3 Secondary circuits pressure 0.145 MPa

Average linear power 29.3 kW/m No. of turbine generator 1

Maximum linear power 49.0 kW/m Steam pressure 13.7 MPa Sodium temperature at the inlet 505 ℃ No. of fuel subassembly 565 of steam generator Sodium temperature at the outlet 309 ℃ Length of fuel subassembly 3 500 mm of steam generator Coolant temperature at the inlet 210 ℃ No. of pins per fuel subassembly 127 of steam generator Coolant temperature at the outlet 490 ℃ No. of radial blanket subassembly 90 of steam generator

Fig. 1 CDFR core layout IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Experimental Fast Reactor 5

Fig. 2 Main heat transfer systems

5) Three decay heat removed systems are connected to secondary circuit, a kind of parallel connec- tion to each loop. These systems ensure that decay heat will be removed by air natural cycle even the plant blackout. 6) A guard vessel and plenty of double deck pipes are adopted. This guarantees the core is under sodium level in accidents. 7) A core melt collection device is used to protect the main vessel. 8) For preventing the release of radioactivity, the upper protection cover is used as a complement. 9) A kind of passive fluid envelop system can avoid the main vessel out of pressure. 10) Siphon device will be used in case of overmuch loss of primary sodium. 11) Comply with the nuclear safety standard, a series of sealed rooms and containment rooms are designed. 12) Digital technology is used in the design of the I & C systems.

Progress of the Generation Ⅳ International Forum (GIF)

YANG Hong-yi, SONG Wei

Taking into account the increase in energy demand worldwide and the growing awareness about global warming, climate change issues and sustainable development, nuclear energy will be needed to meet future global energy demand. In order to provide a sustainable development of nuclear energy, the Generation IV nuclear energy system was put forward. In July 2002, under the proposal of the USA, nine countries signed the Charter of GIF, whose purpose is to lead the collaboration of the world’s leading nuclear technology nations to develop next generation nuclear energy systems. Now, the member have increased to thirteen include China. In December 2002, GIF published the Technology Roadmap for Generation Ⅳ Nuclear Energy Systems (Roadmap), which identified six promising generation Ⅳ nuclear energy systems, include sodium fast 6 Annual Report of China Institute of Atomic Energy 2007

reactor (SFR), very high temperature reactor (VHTR), gas fast reactor (GFR), lead fast reactor (LFR), molten salt reactor (MSR), supercritical water cooled reactor (SCWR). Figure 1 show the organization of GIF. The policy group (PG) is the administration leader, and the expert group (EG) is the technical consultant. There are three working groups (MWGs) of GIF— economic modelling (EMWG), proliferation resistance and physical protection (PRPPWG), and risk and safety (RSWG). The task of the MWGs is to design and implement methodologies for evaluating the GIF systems against the goals defined in the Roadmap in terms of economics, proliferation resistance and physical protection, and safety. In according to the six systems identified in Roadmap, GIF set up six system steering committees (SSC). Every SSC work out their System Research Plan (SRP) and set up the project groups in according to their own research. Figure 2 shows the contractual architecture. Every member must sign the Chart, Framework Agreement (FA), System Arrangement (SA) and Project Agreement (PA) in turn. Each signatory can either do the research separately or work with other signatories. Among signatories, information and technology are sharable, which can accelerate the R&D greatly. Up to now, the negotiations of SFR, VHTR, GFR and SCWR are favoring. Several country signed the SA, and published the specific SRP. The negotiations of LFR and MSR are undertaking.

Fig. 1 GIF organization

Fig. 2 GIF contractual architecture

IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Experimental Fast Reactor 7

Preliminary Calculation and Analysis of China Demonstration Fast Reactor Core Physics

LI Ze-hua, TANG Zhong-liang, ZHAO Jin-kun, ZHOU Ke-yuan, HU Yun, GANG Zhi

The paper presents core physics scheme of 820 MWe sodium cooled CDFR (China Demonstration Fast Reactor), which, with better safety and economics, can meet the requirements of the Generation-Ⅳ nuclear system. Specifically, it has the following features: 1) CDFR uses MOX fuel and the breeding ratio of reactor is increased; 2) The CDFR core has 3 zones as inner core, medium core and outer core, and the enrichment of Plutonium is increased from inner core to outer core, by which the distribution of radial neutron flux is flattened and the fuel discharge burnup is increased; 3) A new passive shutdown system is introduced to improve safety, which means there are three independent core shutdown systems, one passive system and two active systems; 4) A negative sodium void reactivity coefficient is achieved, improving inherent safety of reactor; 5) The reactor’s cycle time is extended as much as possible to increase breeding ability and load factor of reactor; 6) Mature experience of foreign countries is used to enhance the feasibility of the reactor design, to shorten construction period and to lower construction cost, for instance, using in-core components of Russian BN-800 reactor. The scheme, presented in this paper, was calculated independently by two independent computing systems and the results accorded with each other well. One calculation system is ERANOS code and JEF2.2 data library from France, its credibility is proven through CEFR core physics calculations. Another system combines the CITATION code and self-produced NVITAMIN-C data library. More than that, by using the same computing system, neutronic characteristics of Russian BN-800 reactor, published by IAEA, were calculated and the results accorded well with IAEA data.

Consideration for Thermal-Hydraulics Limiting Design Parameters of SFR Plant

LIU Yi-zhe, YU Hong

With a series of principles, the thermal-hydraulics design criteria of SFR plant has been considered and described in this paper. The primary objective of thermal-hydraulics design is to ensure that adequate flow of coolant is passed through each subassembly and some other components, and ensure the residual heat could be removed properly. The maximum velocity in the reactor block must be no more than 12 m/s to avoid cavitations, flow-induced vibration, and erosion and corrosion problems. And each subassembly must not float off in any condition. The temperature difference in mixing region is less than 47 ℃. And the temperature difference between two adjacent subassemblies should does not exceed 110 ℃ during their 8 Annual Report of China Institute of Atomic Energy 2007

life-time. If that temperature difference is large than 20 ℃ , mechanics calculation is needed in case bend and distortion. In any condition, there must be no coolant boiling in any channel of the core. And whole coolant boiling is prohibited strictly in accident. The maximum temperature of the fuel should be restricted to the melting point in normal operation, with 3σ rule. And the maximum enthalpy value should be less than the permission value in accident. The linear power of the fuel rod is limited to 59 kW/m in the maximum excess power event. The design criteria of maximum cladding and pellet temperature in different subassemblies are showed in Table 1.

Table 1 Maximum cladding and pellet temperature

Clad mid-wall hotspot temperature Pellet hotspot temperature Subassembly type Limit/℃ Rule Confidence/％ Limit/℃ Rule Confidence/％

Fuel 700 2σ 95.45 2 610（MOX） 3σ 99.73

Blanket 680 2σ 95.45 Melting Point － －

Control rod 550 2σ 95.45 Melting Point － －

Reflector － － － 1 400 － －

Shielding 550 2σ 95.45 Melting Point － －

Internal storage 680 2σ 95.45 Melting Point － －

Reliability Analysis of Cooling Water System of CEFR Based on GO Methodology

YANG Li-fang, YANG Hong-yi

Reliability is an important indicator for assessing the performance of a reactor system. The GO methodology is a success-oriented system reliability analysis method. It can analyze the reliability of the multi-state, related-time, complicate systems, especially in flow system. It can reflect the essence of the system more distinctly. The main function of the cooling water system of CEFR is exporting the heat released by the equipments in the nuclear island. The reliability of the system is concern with the normal operation of the reactor. There are many redundancy-spare components in the system, traditional methodologies have huge constraints in analyzing reliability of the system. The water flows circularly in the cooling water system which is obvious input-output. Therefore in this paper we propose the cooling water system of CEFR reliability analysis method based on GO methodology. Quantitative formulas of redundancy-spare components are deduced combing with Markov model and characteristics of multiple redundancy-spare components in the system. Through GO methodology analysis system, the GO figure is protracted, quantitative results of cooling water system was calculated in the reliability analysis. The analysis proves that in principle GO methodology is in conformity with strict logical inference, it is of advantage to analyze redundancy-spare components. The GO methodology is a new method for the reliability analysis of a reactor system. IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Experimental Fast Reactor 9

Development of V2MB Used to Linearized Stress Results From ANSYS

WEN Jing, YU Hong, WANG Ming-zheng

The stresses should be classified before structural intensity evaluation of the equipments in the design of boiler and pressured vessel according to corresponding codes, such as ASME Code, RCC-M Code and JIS Code. The stress results should be linearized through the shell thickness to membrane stress and membrane-plus-bending stress which is used to evaluate the structural intensity. To meet the need of engineering and scientific research, the FEM program Technostar/VENUS, which is developed by Japanese engineers, has been purchased by China Research Center of Fast Reactor. This program has very powerful function. It can carry out FEM modal analysis of the complicate system which has more than 10 000 000 DOFs. However, it can not provide the linearized stress through the shell thickness but the nodal stress components and principal stresses in Excel file, which is not enough for the structural intensity evaluation. In this paper, a new program V2MB has been developed to linearized the stress components, principal stresses and stress intensity through the shell thickness by Least Square Method to provide the membrane stress and membrane-plus-bending stress. This program has been compared to another general purpose FEM program ANSYS and analysis solution for some special conditions. The results agree with each other very well. The validity of V2MB has been proved.

Preliminary Analysis of Thorium Utilization Features in FBR

GANG Zhi, ZHAO jin-kun, CHEN Yi-yu, ZHOU Ke-yuan

With increasing development of the nuclear power in the world, the nuclear energy shall play a more important role to meet the energy ever-growing demands. However, to keep the sustainable, large-scale development of nuclear power, the nuclear resources supply is the first question. The current global affordable uranium resources is estimated about 4 million tons, which can’t support the today’s total nuclear power operation more than 100 years, so it is imperative to deal with the nuclear resources worry. The approaches may be from two aspects, one is to expand the exploration of the uranium resources and find the new affordable uranium resources in the world, the another is to consider and develop the exploration and utilization of thorium resources with a bigger amount than uranium in the earth. Natural thorium does not have intrinsic fissile content unlike uranium and can’t be burned directly as fuel, but 232Th as a fertile nuclide can convert to 233U by β decay after absorbing neutron like 238U, and the new nuclide 233U is a fissile material with excellent nuclear properties to be used as energy source. So the most important aspects for utilization of thorium as following: firstly, which type of reactor can produce 233U more efficiently with a reasonable manner; secondly, what kind of reactor is suitable for burning 233U economically. This article mainly discusses the utilization of thorium in the fast neutron spectrum with MOX, (Pu, 232 233 Th)O2 driven fuels, including the basic physics features of Th and U, the estimation of breeding 10 Annual Report of China Institute of Atomic Energy 2007

features with referenced fast reactor CPFR and so on. According to the basic nuclear features and preliminary calculations, we can draw the following conclusions. 1) The absorption cross-section for fast neutrons of 232Th (0.38 barns) is slightly more than that of 238U (0.33 barns). Hence, it is possible to realize the breeding with 232Th through an economic manner in fast reactor. However, compared the physics features of 233U between thermal and fast spectrum, 233U should be burned more economically in the thermal reactor with far greater fission cross section. 2) As preliminary physics calculations in this article show that two cores can breed the fertile based on the thorium, and their breeding ratios also are attractive for enlarging fissile resources. The MOX breeder core may be more reasonable and feasible in two modes, because this way makes the fertile materials 238U and 232Th together convert to the fissile effectively and enhance the resources utilization through existing technique. In addition, the MOX core has a small initial fissile loading than the plutonium core. The output and purity of 233U produced in the reactor is a paradox, their balance should be considered to meet a variety of user requirements.

Preliminary Strategy Study on Thorium Utilization Based on FBR

ZHAO Jin-kun, GANG Zhi, ZHOU Ke-yuan, CHEN Yi-yu

Converted to 233U in reactors, thorium can be adopted to real nuclear fuel. The key for using thorium efficiently is to choose the proper reactor type and fuel cycle to produce and burn 233U. This article analysis some different reactor types with Th/U cycle adopting different nuclear materials based on fast reactor technology, to optimize the fuel cycle for using thorium resource in fast reactors. There are 4 modes which are different on matching reactor types, including once-through by PWR, Th-U cycle by PWR, U-Pu cycle by PWR&FBR, Th-U cycle by PWR&FBR and U-Pu-Th-U cycle by PWR&FBR, listed in the following charts. There are two merits which 233U is produced by FBR through transforming 232Th, one of which is the high conversion efficiency, and the second is the conversion of 233U by high purity. At the same time, from the comparison of several U-Th fuel cycles, the conversion of 233U with FBR is more efficient than the conversion with only PWR.

Table 1 Difference of 4 modes

Year PWR FBR PWR(U3) Total capacity

2000 0 0 0 0

2010 20 0 0 20.00

2020 40 0 0 40.00

2030 60 49.59 0 109.59

2040 60 83.79 107.07 250.85

2050 60 117.99 275.18 453.16

2060 40 147.06 504.72 691.78

2070 20 164.72 783.69 968.42

2080 0 170.99 1 095.40 1 266.39

2090 0 170.99 1 424.65 1 595.64

2100 0 170.99 1 768.03 1 939.02 IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Experimental Fast Reactor 11

Fig. 1 Total load capability amplitude of different fuel cycle modes mode：×—1；◆—2；*—3；▲—4

For the above reasons, as the conclusion it’s a reasonable use of thorium resources mode that plutonium will be converted firstly by PWRs with thorium for fast reactor fuel loading and also thorium is loaded in FBR for more 233U, then thorium fuel rods contained 233U is made for the other thermal reactor (PWR or HTGR). This thermal reactor/fast reactor combination makes it possible that FBRs breed 233U efficiently and quality, and thermal reactors consume 233U economically.

Analysis of Measurement Data for Neutron Counting Assembly on Reactor

ZHAO Yu-sen, FAN Zhen-dong

The neutron counting assembly was linked with fission ionization chamber and its performance characteristics were tested on the 49-2 Swimming Pool Reactor. A lot of data were obtained. The data were treated and analyzed. Choosing the threshold value of discriminator is 0.652 V initially, the plateau curve of neutron counting assembly is measured at reactor power 3.2 μA. The data treatment indicates that the start point of plateau is 210 V and the operation voltage is determined at 300 V. When the operation voltage is at 300 V and the reactor power is at 1.85 μA, the threshold value curve of neutron counting assembly is measured. The flat part is not presentation in the threshold value curve. In order to obtain good ratio of signal to noise, the threshold value is chose between 0.6 and 1.0 V. When the operation voltage is at 300 V and the threshold value is 0.652 V, the linearity between the reactor power and the count rate is measured. The parameters are obtained by the least-squares fit as follows, A=367.5±360.5, B=852.9±21.8, R=0.999 02. The least-squares fit result indicates that the relation between the reactor power and the count rate is linear. In order to determine the operation condition of neutron counting assembly is normal or not, 75 data are measured when the operation voltage is 300 V, threshold value is 0.652 V and reactor power is 0.8 μA, and then the Shapiro-Wilk test and the Gauss fit are made for these data.

The experimental average value and the standard deviation are xe = 7 135.1, σ x =16.6 respectively 12 Annual Report of China Institute of Atomic Energy 2007

for these data. For given confidence level 0.05 the results of the Shapiro-Wilk test are W=0.992 91, P=0.993 31. This result indicates that the measured data obey normal distribution. The results of Gauss fit are shown in figure 1 for these 75 data. The average value and the standard deviation are x = 7 146.8, σ=16.3.

Fig. 1 Results of Gauss fitting

According to the analyses as above the operation of the neutron counting assembly is normal.

Preparatory Calculation of Noise Analysis on CEFR

FAN Zhen-dong, ZHAO Yu-sen

The purpose of noise analysis on CEFR is to acquire parameter of reactor and monitor the possible abnormity, the noise analysis doesn’t interrupt the running of reactor. The basis noise analysis can be actualized easily by the instrument used in physical starting and running. We can discover experience noise and found noise model, this will be significant for the future.

1 Neutron noise analysis on CEFR The neutron noise analysis on CEFR can be carried into execution according as the neutron pulse from the ionization chambers used in physical starting, the neutron pulse from the neutron field in reactor is amplified by the front amplifier and the main amplifier, the last, it is trimmed into TTL pulse easy to be acquired. In all the instruments of physical starting lab, the physical starting acquisition system is the best suitable to do the neutron noise analysis. The physical starting acquisition system is assembled from a PCI counter/timer device NI6602 and a high-powered computer, it can work with customization software as different functions. The NI6602 contains 8 channels counter/timer, it can count 80 MHz pulses, it can count without gap, and the minimal counter timing can be 12.5 ns, and it can be setup into 7 channels scale without any change on hardware. With reference to the features of the instrument, experiments can be done earlier are list as follows: 1) Rossi-a method; 2) Variance-to-mean method; IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Experimental Fast Reactor 13

3) Zero probability method; 4) Correlation, (1) detecting and application of self correlation function, (2) detecting and application of mutual correlation function; 5) Frequency spectrum analysis.

2 Mechanical vibration analysis on CEFR This experiment can be carried into execution according as the signal from the acceleration sensor on the cover of the reactor, the low difference voltage signal is amplified into 4-20 mA current signal, then sent to acquisition system by the cable. The last, it is turned into dates in computer for the future analysis. The method of mechanical vibration noise analysis also contains self correlation analysis and mutual correlation analysis, by this analysis, the relation between the noise and the state of the reactor can be known, and it will helpful to found the noise model. By this way, incidental can be discovered and analyzed. For example, the noise of the pump at different rotate speed can help person to recognize whether the pump is normally, another example, incidental vibration can be the represent of some froths in Na coolant.

Treating Experimental Data of Inverse Kinetic Method

CHEN Xiao-liang, ZHAO Yu-sen

Inverse kinetic method is one of the important methods for measuring reactivity in the reactor. The reactivity and the effective source strength can be determined by double parameters accordant calculating experimental data of inverse Kinetic method when the space effect is not obvious; there is external source in the core and the power is low. The instantaneous reactivity can be determined by using effective source strength.

1 The theory of double parameters accordant calculation From the point-reactor neutron-kinetics equation irrelevant the space effect the expression of double parameters accordant calculation can be concluded. The reactivity and the effective source strength can be determined.

2 Writing the computer code

The computer code was written with Fortran 95. λi, βieff, Λ can be input as the constants. βeff, ai can be calculated by the computer code. Channel width, ΔT, is a various parameter which can be input after the cues of the computer code.

3 Calculating the example The expressions and the computer code are validated by using the dada of zero power facility BFS-1 in Russia. The experimental data irrelevant the space effect was chosen to treat by double parameters accordant calculation. Fig.1 is the curve of neutron count rate vs. time of data 1 and Fig.2 is the curve of reactivity vs. time of data 1. After comparison to the results in Russia the error is under 7%. 14 Annual Report of China Institute of Atomic Energy 2007

Fig. 1 Curves of neutron count rate vs. time of data 1 Fig. 2 Curves of reactivity vs. time of data 1

4 Conclusions After comparison between double parameters accordant calculating experimental data of inverse Kinetic method in zero power facility BFS-1 and three parameters accordant calculation by Russian, the expressions of double parameters accordant calculation is correct and the computer code is reliable, which can be used to off-line treating experimental data of inverse kinetic method with the neutron source.

Development on Reaction Rate Relative Distribution for Experimental Data Processing Program

WANG Da-fei, HU Ding-sheng

The advanced data processing program is developed in this study. It is prepared for the reaction rate relative distribution experiment of CEFR. Firstly, the calculation expression of the reaction rate relative distribution experiment is deduced. The normalized power factor is inducted into the calculation expression. The irradiation powers of each radial measurement dots are normalized to the same level by the normalized power factor；Secondly, the curvature fitting calculation formula of the thermal neutron reactor axial and radial in-core neutron fluence rates relative distribution is deduced；Finally, the three cubed spline function fitting calculation expression of Fast-Neutron Reaction neutron fluence rates relative distribution is deduced. The calculation expression of the reaction rate and the curvature fitting calculation formula of the thermal neutron reactor axial and radial in-core neutron fluence rates relative distribution are carried out by the VB6.0 programming. The three cubed spline function fitting calculation expression of Fast-Neutron Reaction neutron fluence rates relative distribution is carried out by the MATLAB 6.0 programming. The function of VB program is evaluated by inputting the data which are obtained through measuring reaction rates relative distribution by radioactivation of Mn-Ni alloy in Heavy Water Zero Power Reactor. The result is satisfied. The function of MATLAB program is evaluated by inputting the data which are obtained through measuring fission reaction rates relative distribution by radioactivation of 235U in БФС-65-1 Fast-Neutron Reaction Reactor. The result is satisfied. IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Experimental Fast Reactor 15

Analytical Method for Determinating Carbon Impurity in Sodium

XIE Chun, JIA Yun-teng, GAO Yao-peng

Sodium is used as a coolant in China Experiment Fast Reactor (CEFR). Carbon impurity in sodium has an influence on physical and mechanical property of materials. So Some countries, such as American, Russia, Japan, France, Germany, India and so on establish own quality standard of carbon in sodium. CEFR’s quality standard of carbon in the first and second sodium loop is not more than 20 μg/g(Ⅰ) and 30 μg/g(Ⅱ) respectively. The analytical method is used to determinate carbon in the first sodium loop, and is suitable to determinate carbon in non-radioactive sodium too. Under the argon atmosphere, sodium samples are put into silica crucibles, then crucibles are placed in a stainless steel distillation pot at 400 ℃ and 6.7×10－3 Pa to remove the sodium. The residue is combusted at 1 000 ℃ or 1 100 ℃ with high pure oxygen. The carbon dioxide formed is collected in an absorption solution of barium chloride (10%) and barium hydroxide (0.01 N), whose pH value equals to 10. pH of the absorption solution gradually reduces along with result of barium carbonate .Eventually the absorption solution is titrated by barium hydroxide (0.01 N) and its pH is increased to 10. The content of carbon in sodium is calculated according to volume of barium hydroxide consumed. Many experimental conditions such as distillation, combustion, quantitative measurement have been studied. Standard addition experiments are carried out with graphite and sodium carbonate standards, the recovery rates are 100.9%±13.3% and 102.7%±10.1% respectively. The average relative arithmetic deviation is less than 10% when this method has been applied to analyse nuclear grade sodium of CEFR. So the method developed meets CEFR’s technical needs for carbon analysis in nuclear grade sodium.

Calibration of China Hydrogen Meter in Argon

HONG Shun-zhang, LUO Rui1 (1 , Beijing 100084, China)

The China hydrogen meter in argon is used for detecting water leakage from third loop to secondary loop in China Experimental Fast Reactor (CEFR). It is a very important on-line impurity detecting instrument for safe operation of the fast reactor. Because the kind instruments only give a signal, it needs calibration by chemical methods. The argon which contains definite concentration of hydrogen is used as standard gas to calibrate the hydrogen meter in argon. The calibrating experiment of the hydrogen meter in argon was carried out in the hydrogen meter experimental loop in Tsinghua University. Some researchers in China Experimental Fast Reactor took part in the work.

1 Hydrogen meter and calibration experimental loop The hydrogen meter consists of a sensor with nickel membrane, a high vacuum system with ion pump and a heat convection loop. The heat convection loop is located on the top of the simulated steam generator. The calibration experimental loop consists of a set of hydrogen injection device, a simulated 16 Annual Report of China Institute of Atomic Energy 2007

steam generator, expansion tank etc. The hydrogen injection device provides argon flow with trace hydrogen. It is obtained by two ways of gas, one is pure argon, the other is the argon which contains definite concentration of hydrogen. The pure argon flow is 170 L/h or 255 L/h in the calibrating experiments; the flow of the argon contained hydrogen is variable and hydrogen content in the argon is 0.104% in the calibration experiments.

2 Experimental procedure 1) Heat hydrogen meter to 480 ℃ and the simulated steam generator to 170-300 ℃. 2) The argon contained hydrogen flows in whole calibration experimental loop and exhaust through a valve on the expansion tank for more than 20 min. Then the stable output of the hydrogen meter can be obtained.

3 Results and analysis

When the argon contained definite amount of hydrogen (p1) flowed in the simulated steam generator, the concentration of the hydrogen in the simulated steam generator increased. About 20 min later, the concentration of the hydrogen reached stable value (p0+p1), the current of the ion pump can be expressed as: 1/2 I=k(p0+p1) +Ib

Where: p0 is initial concentration of the hydrogen in the simulated steam generator (Pa); p1 is hydrogen partial pressure in the mixed calibrating gas (Pa); I is current of the ion pump after injecting hydrogen

(μA); k is coefficient; I0 is base current of the ion pump (μA). Table 1 lists the results of calibration experiments for china hydrogen meter in argon.

Table 1 Results of calibration experiments for China hydrogen meter in argon

Date 2007-03-27 2007-03-28 2007-03-29 2007-04-04

concentration of the hydrogen in argon before mixing 0.104 0.104 0.104 0.104 0.104

with pure argon (%H2/Ar)

Flow of pure argon (L/h) 255 170 170 170 170

Temperature of nickel membrane (℃) 428 450 450 450 450

Temperature of simulated steam generator (℃) 210 172 172 176 172

Duration of injection hydrogen (min) 40 60 30 30 30

Flow of argon contained definite amount 4.49 4.48 2.88 6.31 1.40

of hydrogen (L/h)

Amount of increase in hydrogen partial pressure p1 (Pa) 1.80 2.67 1.73 3.72 0.85

Duration of injecting hydrogen (min) 20 60 30 30 30

Base current of the ion pump (A) 8 8 8 8 8

Current of the ion pump before injecting hydrogen 84 54 47 47 26

current of the ion pump after injecting hydrogen (max, A) 93 67 56 68 38

initial concentration of the hydrogen 7.97 4.95 4.12 3.40 0.75

in the simulated steam generator p0 (Pa)

1/2 1/2 p0 (Pa ) 2.22 2.03 1.84 0.87

concentration of the hydrogen in the simulated steam 9.77 7.62 5.85 7.12 1.60

generator after injecting hydrogen (Pa)

1/2 1/2 (p0+p1) (Pa ) 2.76 2.42 2.67 1.26 IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Experimental Fast Reactor 17

Because the temperature of the nickel membrane is low on March 27, the results can not be used in the calibration curve of the hydrogen at the temperature of 450 ℃. According to the results in table 1, the calibration curve of the hydrogen at the temperature of 450 ℃ has been obtained in Fig 1. We can see that p1/2 is good linear with current of the ion pump. The intercept of the curve is 8.4 A, it is very close to 8 A of experimental results.

4 Conclusion During the calibration of the hydrogen, it has been found that the containers which are used for storing argon contained hydrogen can absorb hydrogen, when the concentration of the hydrogen is low, this action is serious relatively. If the containers keep high temperature the effect of hydrogen absorption by the containers can be negligible. Using the argon contained definite amount of hydrogen mixed with pure argon as injection hydrogen gas the good results can be obtained.

Fig. 1 Calibration curve of hydrogen at temperature of 450 ℃

18 Annual Report of China Institute of Atomic Energy 2007

China Advanced Research Reactor (CARR)

Piping Stress Analysis of Coolant Purification System in China Advanced Research Reactor

DAI Shou-tong, WANG Jun

The piping of the heavy water purification system in CARR is complicated and giant. It is taken apart to some separate calculating models of stress analysis (Fig. 1), and each model has been analyzed and evaluated solely. Because the pipelines are thin and the flexibility of piping is nice, the requirements of the weight loads and the thermal loads can be satisfied easily, at the same time the piping rigidity is bad so it is difficult to satisfy the aseismatic requirements. The analysis makes good use of the powerful functions of the software PIPESTRESS such as the mode shape display, the rigid supports are set at the most appropriate places in order to increase the local rigidity and the aseismatic capability of the piping, the aseismatic effects are achieved by using supports as less as possible, at last all the results of the piping have been accorded with the correlative requirements of the criterion (Table 1).

Fig. 1 System split model

Table 1 System results

Code level Max stress/MPa Allowable stress/MPa Stress ratio

Design 54.67 177 0.309

Level A 73.59 295 0.249

Level B 32.44 177 0.183

94.89 212.4 0.447 IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Advanced Research Reactor 19

Piping Stress Analysis of Heavy Water Purification System in China Advanced Research Reactor

DAI Shou-tong，WANG Jun

The pipelines of the heavy water purification system (Fig. 1) in CARR are very dense and thin, the flexibility of piping is nice and the rigidity is bad. The requirement of static loads can be satisfied easily but that of the dynamics loads cannot. The stress analysis principles of the static cases first and then the dynamic cases are adopted to adjust the supports. The floor response spectrum method which has a higher precision is adopted to get the aseismatic results though the pipelines are thin. The piping rigidity is heightened and the aseismatic capability is increased through setting the axes restricting supports and the anchors at the part where the vibration is strong, so the piping can resist the certain level concussion caused by the occasional loads, and the piping aseismatic requirements have been satisfied. The results are listed in Table 1.

Fig. 1 System piping model

Table 1 System results

Code level Max stress/MPa Allowable stress/MPa Stress ratio

Design 43.82 195 0.248

72.1 195 0.407 Level A 113.21 325 0.384

168.47 325 0.571 Level B 121.25 234.2 0.571

Test 44.17 279.5 0.158

20 Annual Report of China Institute of Atomic Energy 2007

Piping Stress Analysis Optimizing of Secondary Cooling Water System in China Advanced Research Reactor

DAI Shou-tong, WANG Jun

To gratify the requirements of the piping installation advancing of China Advanced Research Reactor (CARR), the supports setting of the secondary cooling water system (SCS) are optimized. The optimizing analysis of the piping is carried through on the principles that the installation will be realizable easily and the stress requirements are satisfied according to the change of the model calculating boundary. The optimizing project (Fig. 1) adjust the places and the types of some supports, not only new supports are not added but the three snubbers (Table 1) set formerly are gotten rid of. The places and the types of supports set on the optimizing project satisfy the demands of the stress analysis in the end (Table 1) and ensure the radication of the supports. So the engineering expenses are cut down and the economical characteristic is heightened.

Outflow system Inflow system

Fig. 1 System optimizing model

Table 1 System results

Code Case Lodes sorts Allowable Outflow system Inflow system

level sorts stress/MPa Max stress/MPa Stress ratio Max stress/MPa Stress ratio

Design Design Weight+Stress 195 55.2 0.283 50.1 0.257 Level A Normal Weight+Thermal 325 124.9 0.384 136.8 0.421 Level B Upset Weight+Thermal 325 187.2 0.576 187.2 0.576 Weight+Seism OBE 234.2 127.2 0.543 108.9 0.465 Test Test stress 279.5 51.1 0.183 47.2 0.169

Piping Stress Integrative Analysis of Reactor Cooling Water System and Secondary Cooling Water System in China Advanced Research Reactor

DAI Shou-tong, WANG Jun

Integrating the piping installation advancing of China Advanced Research Reactor (CARR), the supports setting of reactor cooling water system (RCS) and secondary cooling water system (SCS) are IMPORTANT NUCLEAR SCIENCE ENGINEERING·China Advanced Research Reactor 21

adjusted synthetically. The two piping (Fig. 1) connect the reactor core and the important equipments, the pipelines of which are interlaced in the compact factory rooms, so the supports radication intervener can occur easily. The stress analysis must satisfy the requirements of the nozzle loads besides that of the piping stress. The practical analysis think over the two piping together，the supports setting make overall plans and take all factors into consideration, the supports are set as less as possible after the reduplicate adjusting and optimizing，in the end the supports radication capability is nicer and the nozzle loads are satisfied with the demands of the equipments besides the piping stress level is lower（Table 1），it comes true that all of the two piping’ security reliability and economical characteristics are integrated fairly well in the two most important piping in CARR.

Fig. 1 System piping layout

Table 1 The maximal stress ratio and maximal nozzle lodes ratio

System Stress ratio Pump Exchanger Inflow SCS 0.576 0.63 Outflow SCS 0.576 0.9 Inflow RCS 0.578 0.92 Outflow RCS 0.437 0.83

Technical Study on Radioisotopes Production of CARR

DING Li, ZHOU Yuan, -lin

The paper focuses on the analysis of important irradiation technology and irradiation safety of radioisotope production within the vertical experiment tubes in CARR by means of MCNP code and the thermal-hydraulic code. Target considerations include target materials, irradiation location, target size and shape, irradiation time, self-shielding, target heat, reactivity disturbance and temperature limits. According to the operation schedule given by the original design, the target loading plan and the quantity of typical radioisotopes such as 131I, 31P, 113Sn, 133Ba, and 133Sm are obtained through calculation. Targets in high specific activity just like 60Co and 192Ir are considered too. In the end the radioisotopes’ yield is given. A simulation targets experiment completed in HWRR has proven the calculation of target heating rate reasonable and the thermal-hydraulic analysis corrective. 22 Annual Report of China Institute of Atomic Energy 2007

Beijing Radioactive Ion-Beam Facility

Progress on Design and Construction of CYCIAE-100

Technology Division of Beijing Radioactive Ion-Beam Facility (Written by ZHANG Tian-jue, LI Zhen-guo, CHU Cheng-jie)

Based on the preliminary design of the 24 sub-systems accomplished in 2006, the detailed design and construction has been carried out in 2007 for a number of those sub-systems of CYCIAE-100. In the meantime, the beam injection experiment of the CRM cyclotron has been conducted, and so does the welding experiment for the 1:1 scale RF copper model cavity, accumulating the engineering technique and experience for the fabrication of RF resonance cavity. Fig. 1 shows the sketch map of CYCIAE-100 after part of the engineering design has been finished.

Fig. 1 Sketch map of CYCIAE-100 after part of engineering design has been finished

1 Design and construction of CYCIAE-100 1.1 Main magnet and its related system The uneven-height structure that applies to the top/bottom yokes is optimized so that the increment of magnet deformation along radius induced by the atmospheric pressure after pumping can be reduced by 41.26% compared to that of an even-height structure. A side wine of 130 mm high has been added to the sector, and taking advantage of this change, the dimension of the main coil is adjusted accordingly. In the previous design, due to the small radial distance IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 23

between the main coil and the sector, the design and installation of the vacuum chamber becomes very difficult. After the adjustment, the problem can be solved properly. Meanwhile, it also helps to avoid the difficulty to drill a long hole on the top/bottom yoke of 775 mm thick for the pumping of the double O-ring structure on the main vacuum chamber. Apart from that, the installation of the main coil becomes a lot easier. The asymmetric shimming bars are designed in a way that makes the most use of the limited space at the outer radium (R>1 200 mm) between the shimming bar and the RF resonance cavity. This design enables to avoid the influence from the coupling resonance on the working path at high energy end in the tune diagram. This kind of asymmetric shimming bar design is a standby solution in case the BH curve of steel is not as good as design specification. Two sets of special measuring tools for main magnet are designed. One is used to measure the angle of the sector, and the other is used to measure the varying gap surface of the sector. Besides, a set of installation tool is specially designed for the shimming bar installation, and the drawing for fabrication has been finished. Based on the existing design of the elevating system for the main magnet, many experts, home and abroad, put forward the advice that it would be more reliable and secure to apply the 4-point elevating solution. The investigation on the worldwide compact cyclotrons above 50 MeV shows that, for the elevating, only IBA adopts the 2-point hydraulic system, all the other applies the 4-point screw jacks elevating system. At present, the design of screw jacks elevating system for CYCIAE-100 has been basically finished with the joint efforts from the engineering experts and technical specialists from laboratories including LNS and TRIUMF, and the factories as well. For the hydraulic design, it is still at the phase of conducting an in-depth discussion with the factory and is supposed to be accomplished soon. The rough machining steel for the sector magnet has been finished by the end of last year. It was transported to Tianjin Port via Lyon in France. For the cast steel fabrication of the top/bottom yokes and return yokes, the contract was signed with CITIC Heavy Machinery Co. LTD. in August 2007, and the casting has been finished for the return yokes and experimental piece of the top/bottom yokes by the end of 2007. From the preliminary analysis of the test result, it shows that the chemical composition of the molten steel meets the requirement of the designed specification, and it is planned that all the fabrication work of the cast steel for the top/bottom yokes and return yokes will be accomplished in the first half of 2008. 1.2 RF system In the March of 2007, the contract was signed for the RF power source and the transmission line for CYCIAE-100. Keeping a constant technical communication with the factory, currently the engineering design has been finished and is ready for the evaluation and fabrication. The adjustment and optimization for the tip of the RF cavity and Dee structure has been finished. Meanwhile we have accomplished the final RF design for the resonance cavity. The detail structure and dimension for the cavity are given and the mechanical design has been done. Besides, we have finished calculating the RF power consumption and the numerical simulation of the temperature distribution on the cavity, and the design of water cooling system. 1.3 Injection and extraction system The main magnet applies the top/bottom yokes of uneven height. Therefore, the dimension of the magnet in the axial direction increases, and the component layout in the injection system should be readjusted. Based on the new structure of the magnet and the corresponding new magnetic distribution, the injection line is redesigned and the calculation for the optics matching is also accomplished. In the 24 Annual Report of China Institute of Atomic Energy 2007

mean time, an in-depth investigation focusing on the theoretic research at the inflector and central region is carried out, including the calculation of the two horizontal emittances in radial and vertical direction respectively, the study on in radial and transverse-longitudinal coupling, vertical focusing, emittance matching, and so on. In the aspect of extraction, the research is further conducted concerning the possibility of extracting beam with energy lower than 70 MeV, and the interface between the small chamber for combination magnet and the main vacuum chamber is re-determined. The dispersion effects during the beam extraction are also studied and through numerical tracking, the beam transfer matrix is calculated from the stripper to the combination magnet. The hill gap of the combination magnet is also re-determined, increasing from 60 mm to 80 mm. As a result, the corresponding interface for the beam line is adjusted accordingly. The efficiency of the stripping foil is calculated, so the thickness of the foil is determined. The temperature rise of the stripping foil is re-estimated. The experiment is carried out to improve the sealing of the target rod and its structure is reconsidered. 1.4 Other aspects For the vacuum system, the preliminary design for the cryopanel system has been finished and the refrigerator selection has been carried out. With regard to the beam diagnostics system, the experimental study on the network based signal acquisition has been performed and so far several functions have been realized, including the input/output of the analog signals, step motor control, network data transmission, and etc. We also finished the work on the processing and compiling of the codes, the practical measuring experiment on the control system of DCCT and double wire scanner and corresponding signal acquisition. So far the design and fabrication of the emittance scanner has been finished too. For the dose monitoring and safety interlock system, the layout design of the devices for radiation monitoring and safety interlock, the installation location and applied method, the passage for the cable and control signal had been designed based on the civil construction plane. The total quantity of monitoring points is summed up and the software monitoring process is designed for the whole system. In the meantime, investigation has been made on the measuring methods and device for neutrons at wider energy range home and abroad.

2 Progress on experimental verification 2.1 Commissioning of the CRM cyclotron Following the fabrication and installation of the hardware for the central region of CYCIAE-100 conducted in 2006, we have accomplished the test of equipments and the experiment on beam injection. For the equipment test, it mainly concerns the experiment of RF power input and the conditioning of resonant cavity. At present, the duty factor is 1/4 only, the system can not satisfy the requirement for a stable CW mode. The beam commissioning problem may lie in the accelerating RF voltage, which is still a distance from the designed value of 50 kV. As a result, the structure of the central region has to be adjusted temporarily, and thus the injection experiment at the central region is carried out accordingly. Fig. 2 shows the layout of the devices and measuring points from the ion source to the central region. The beam diagnostics system includes the Faraday Cup down stream of the ion source, stop target, four-sector collimator, spiral inflector along the injection line, and several internal targets at the central region, radial probe and stripping target. The beam commissioning result of the injection line is shown in Table 1. It can be seen that the total DC injection efficiency, including the injection line and the spiral inflector, is approximately 94%. The IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 25

efficiency is about 75% before the beam is limited by the collimator at the entrance of the solenoid. When the beam intensity is 0.70 mA, a beam of about 0.50 mA can be obtained at the exit of the spiral inflector. After passing through two accelerating hills, the beam can reach about 60 μA. Therefore, it can be estimated that the RF acquisition phase is about 42°. When accelerated for 8 times, in other word, the beam completes its traveling at the central region, taking into account the RF duty factor, it can be deduced that the beam intensity is about 40-50 μA according to the measuring result. Currently the RF power amplifier and water cooling system of the cavity are being improved. If the accelerating Dee voltage can be further raised, the beam intensity of the internal target of the machine can increase significantly.

Fig. 2 Layout of devices and measuring points from ion source to central region

Table 1 Beam test result along injection line

Ion source Entrance of solenoid Four-sector collimator After spiral inflector

0.7 mA 0.55 mA 0.01 mA 0.53 mA

2.2 Experimental verification of the 1:1 scale model cavity So far the fabrication and part of the welding of the 1:1 RF metal experimental cavity have been finished (Fig. 3). The welding of the outer conductor of the cavity has been completed. However, since the welding of the Dee adopts silver-copper solder under atmospheric environment and oxygen-acetylene flame heating, it leads to some problems such as partial crack, etc. Currently we have reached an agreement with the factory that the welding will be taken inside the furnace and heated under vacuum condition. 26 Annual Report of China Institute of Atomic Energy 2007

Fig. 3 Welding pieces of 1:1 scale model cavity

In order to drive the 1:1 scale model cavity, the commissioning as well as LLRF control work should be done to the 44 MHz RF amplifier. Till now the recovery work for the desktop experiment of the LLRF control system has been finished. The PCB design has been improved, and now the new PCB board is being made. In general, the work concerning the CYCIAE-100 project, including the design, fabrication and experimental verification, has progressed at the right track in 2007. For the year followed, our focus will be on the engineering design of the major systems and the fabrication of the crucial pieces. It is anticipated that all the steel for the main magnet should be finished, and a series of work will be carried out, including the fine machining of the main magnet, the fabrication of the 100 kW RF amplifier and the transmission line system, the manufacture of the RF resonance cavity and the experimental verification of the cryopanel system.

Design and Construction Progress of Main Magnet for CYCIAE-100

ZHANG Tian-jue, LU Yin-long, ZHONG Jun-qing, CHEN Rong-fan, WANG Chuan, JING Wei, LIN Jun, CHU Cheng-jie, LI Zhen-guo, ZHOU Zheng-he, YANG Jian-jun, SONG Guo-fang, XING Jian-sheng, WEI Su-min, YAO Hong-juan, CAI Hong-ru, YANG Fang, WANG Zhen-hui

Given the fact that the successful design and construction of the main magnet for CYCIAE-100 is of primary importance to the whole project, the magnet-centered work has been given great emphasis by the Technology Division of BRIF throughout the process. In 2007, the design and construction progress of the main magnet is summarized as follows.

1 Design aspect The solution to the main magnet design was determined in 2006, after intensive work had been conducted on investigation of similar cases and communication with specialists regarding possible approaches to be taken. The features are as follows. 1) Compact integral structure, straight edge sector, consistent changing hill gap of sector magnet; 2) The core parts, such as the sectors, take use of forged pure iron. The top/bottom yokes and return yokes adopt GB 8# Steel in the light of China standard and casting piece can be considered for use; IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 27

3) The top/bottom yoke will be of uneven height along the radius, so that the hill gap deformation caused by atmospheric pressure, the weight of the magnet itself and electromagnetic force can be reduced effectively. Based on the solution above, we have carried out detailed work on the design concluded in several aspects listed below. 1.1 Structural optimization on the top/bottom yokes of uneven height The structure of the top/bottom yokes of uneven height has been optimized to reduce the magnet deformation under the condition that the magnetic flux is guaranteed and the total weight of the top/bottom yokes remains unchanged. The five typical models in the design are shown in Fig. 1. The magnetic filed distribution is analyzed through numerical method, and thus the electromagnetic force between the sectors is 420 t in total. The upper part of the magnet weighs 170 t, and after pumping, the atmospheric pressure on the top/bottom yokes is 120 t. Through the FEM analysis it shows that the structure of uneven height can effectively reduce the magnet deformation. The result of the deformation from different models is listed in Table 1, in which the electromagnetic force, the gravity of the magnet and the atmospheric pressure at the inner radius (R=25 cm) and outer radius (R=200 cm）are given respectively. Also illustrated here are the deformations and their differences (δd) when the electromagnetic force and gravity are exerted on the magnet. Since the magnetic mapping is conducted in the atmospheric environment, while the cyclotron operates at high vacuum condition, the vacuum compensation is crucial for the mapping and shimming. Taking all the factors into account, Model 5 is finally chosen, and compared to the structure of even height, the former can reduce the deformation difference by 41.26%.

1 2 3 4 5 Fig. 1 Five typical models in design

Table 1 Deformation comparison of 5 models

Deformation at R=25 cm/μm Deformation at R=200 cm/μm

3 Model Weight of top yoke/t Magnetic force, Magnetic Magnetic force, Magnetic force, 10 Slope δd δd gravity, vacuum force, gravity gravity, vacuum gravity

1 130.0 299.25 230.60 68.65 80.80 63.01 17.79 －0.291

2 130.0 176.81 142.90 33.91 56.14 45.80 10.34 －0.135

3 130.0 202.31 162.00 40.31 60.73 49.01 11.73 －0.163

4 129.1 209.71 165.20 44.51 63.09 50.03 13.06 －0.180

5 129.3 210.27 165.10 45.17 63.51 50.24 13.27 －0.182

1.2 Adjustment of the structure parameters for the main coil Due to the fact that a wing of 130 mm in height is added to the sector, the dimension of the main coil has to change accordingly. The height increases from 310 mm (22 layers) to 362 mm (26 layers), and the 28 Annual Report of China Institute of Atomic Energy 2007

radius is reduced from 311 mm (22 turns) to 271 mm (18 turns). As a result, it turns out to be 468 turns in total instead of 484 turns in the previous design. The numerical simulation calculation on the magnetic field shows that when the total number of ampere turns is 29 800, and it will satisfy the requirement for the main magnetic field. The advantage from the adjustment of the main coil structure mainly concerns three aspects below. 1) The previous design has a problem with the distance in the radial direction between the main coil and the sector, which is too small and thus results in the difficulty for the design and installation of the vacuum chamber, whereas the new design has overcome this problem successfully. 2) The previous double-layer seal pumping method has been changed for the main vacuum chamber. It has lowered the engineering level pertaining to the pumping by avoiding drilling slits on the top/bottom yoke of 80 mm thick. 3) It makes it easier for the installation and positioning of the main coil itself. 1.3 Asymmetric design of the shimming bar Previously the main magnet adopts the straight edge sector design without helix angle. If the BH curve could not satisfy the design requirement or the ultra difference phenomenon occurs during the manufacture of the sector angle, the vertical oscillation frequency is likely to decrease at the larger radius and thus risks the occurrence of coupling resonance. In the current design, some space is reserved between the shimming bar and the resonant cavity at the outer radius (R>1 500 mm), which can be used to design the asymmetrical shimming bar, so that the harmful resonance can be effectively avoided in the construction. The essence of the asymmetric shimming is to provide a helix angle to raise the vertical free oscillation frequency, which is proved effective by beam dynamics study. Figure 2 demonstrates the comparison of the angle width between the asymmetric and symmetric shimming bar. It can be seen that the corresponding vertical free oscillation frequency increases apparently, as is shown in Figure 3. For this kind of asymmetric shimming bar design, the structure and parameters of the main magnet remains unchanged. What we need to do is to change the 8 shimming bars out of the 48 related to the roughcast dimension, in which the arc length at the large radius increases approximately 27 mm.

Fig. 2 Comparison of angle width between Fig. 3 Oscillation frequency comparison between asymmetric and symmetric shimming bar isochronous shimming and asymmetric shimming

1—RF liner; 2—Asymmetric +; 3—Symmetric; 1—Asymmetric νz; 2—Symmetric νz;

4—Asymmetric －; 5—Pole edge 3—Symmetric νr/2; 4—Asymmetric νr/2

1.4 Design of measuring tools and fixtures In order to ensure the processing precision of the main magnet, we have also carried out the design IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 29

for two sets of specific measuring tools applied in the construction. One is used to measure the sector angle, and the other is used to measure the hill gap surface of the sector. To guarantee the installation precision of the shimming bar, a set of the installation tool is to be designed for the shimming bar and so far the draft of fabrication drawing has been finished. 1.5 Design improvement of the elevating system for the main magnet Based on the original design of the elevating system, many specialists, home and abroad, put forward their views that the 4-point raising is more reliable and secure for the whole system. When investigating the worldwide elevating system solutions of cyclotrons above 50 MeV, we notice only IBA adopted 2-point hydraulic system, and all the other cyclotrons of integral structure applied 4-point screw jacks. At present, the 4-point elevating can be realized through two solutions, screw jacks and hydraulic elevating systems. Currently the screw jacks based design has been basically finished through joint efforts from engineering designers and factory technicians home and abroad. For the hydraulic solution, an in-depth communication with the factory is being carried out and the design is supposed to accomplish shortly. Meanwhile, the first edition of the construction design has been finished and we have turned it over to the potential manufacturers for necessary discussion on engineering techniques.

Fig. 4 Photos of sector roughcast in early Oct. 2007

2 Construction progress In February 2007 the contract of the sector roughcast for the main magnet was signed with Industeel, a French manufacturer. By the end of 2007, the fabrication has been finished and transported to Tianjin Port. A visit was arranged to visit the mill in France in October 2007 to inspect the fabrication status, and the roughcast at that time is shown in Figure 4. The hot process and FCM cutting of the dimension size 30 Annual Report of China Institute of Atomic Energy 2007

have been accomplished to the schedule. The test result from the manufacturer of the chemical composition of the molten steel is shown in Table 2.

Table 2 Test result of chemical composition of molten steel

Roughcast w(C)/% w (Mn)/% w (Si)/% w (Ni)/% w (Cr)/% w (Mo)/% w (Al)/% w (S)/% w (P)/%

15660# 0.01 0.29 0.17 0.06 0.05 0.01 0.036 0.008 0.005

15638# 0.01 0.29 0.18 0.06 0.04 0.01 0.035 0.01 0.005

15630# 0.01 0.3 0.17 0.07 0.06 0.03 0.04 0.005 0.007

15623# 0.01 0.3 0.18 0.07 0.06 0.02 0.042 0.002 0.005

Requirement 0.06 0.35 0.2 0.08 0.08 0.4 0.02/0.06 0.02 0.025 from contract

The contract dealing with the roughcast fabrication of the top/bottom yokes and return yokes was signed with Zhongxin Heavy Machine Co. in August, 2007, and the casting has been finished for the return yokes and experimental piece of the top/bottom yokes by the end of last year. From the preliminary analysis of the test result, we can see that the chemical composition of the molten steel meets the technical requirement listed in the contract, as illustrated in Table 3; and it is planned that all the fabrication work of the roughcast for the top/bottom yokes and return yokes will be accomplished in the first half of 2008.

Table 3 Chemical composition of molten steel for experimental piece of top/bottom yoke roughcast

w(C)/% w(Mn)/% w(Si)/% w(Ni)/% w(Cr)/% w(Al)/% w(S)/% w(P)/% w(Cu)/%

Roughcast 0.09 0.5 0.23 0.11 0.05 0.019 0.004 0.009 0.08

Requirement 0.11 0.35/0.65 0.37 0.25 0.1 0.1 0.035 0.035 0.25 from contract

Test Stand Commissioning for CYCIAE-100

Technology Division of Beijing Radioactive Ion-Beam Facility (Written by LI Zhen-guo)

The past year has witnessed an essential progress achieved at the test stand for CYCIAE-100, a central region model (CRM) cyclotron. All equipments have been installed and inspected. The preliminary beam test shows that 75% of the beam transportation efficiency from external ion source to the exit of inflector has been obtained and the H－ beam injected is captured and accelerated by RF field and goes out from the central region. This CRM cyclotron will serve as a complete research platform of magnet, RF device, injection, extraction, central region, control and beam diagnostics both for equipment structure designs and for verification of beam dynamics calculations. Figure 1 gives an overall picture of the CRM cyclotron. The CRM cyclotron for CYCIAE-100 set up in Building 201# is a small perfect machine including all relative systems with extraction energy of about 10 MeV. Its main magnet was installed in March of 2006. The magnetic survey and shimming was completed at middle of the same year. The central region, main vacuum chamber and RF cavity were assembled by the end of 2006. IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 31

Fig. 1 CRM cyclotron for CYCIAE-100

The major task related to installing and specification test of equipments of the CRM cyclotron was completed in the year of 2007, which mainly involves the following items. 1) Fixing of RF power transmission line, power coupling capacitor, cavity frequency fine tuning devices. Measurements of RF cavity parameter at cool status, test of RF generator with dummy load and with real RF cavity, specification improvement of RF generator. 2) Installation of flexible cable trailer on main magnet, laying down cables, water pipes, pneumatic tubes, installing other equipments including power supplies, water distribution, pneumatic system, vacuum devices, control, beam diagnostics, radiation monitors and so on. Function tests of above systems. 3) All vacuum problems have been solved. Many leaking places discovered by leak detecting are reasonably treated. As a result, 5.8×10－5 Pa for main vacuum chamber and 1.0×10－4 Pa for ion source and injection line have been obtained. 4) Assembling and testing of external H－ ion source and injection line. A big progress concerns the two quadrupoles at injection line which are successfully built up and put into operation after many experiments that last for a long time due to strict limitations of space, structure, electrical isolation and high vacuum sealing. 5) RF power feed-in test and RF cavity conditioning. RF system is one of the key parts for the CRM cyclotron. During the RF power feed-in test, the following work has been done: coupling capacitor optimization, replace of flexible coaxial transmission line with a rigid one, improvement and calibration of directional couplers, revision of RF pickup loops, measurements of shunt impedance. During RF cavity conditioning, a series of work has been involved. The operation starts at pulse mode and then the RF occupation ratio is gradually increased to weaken multi-electron effect. Improvements have been made on short plate structure, Dee tip and its bridge in order to reduce frequency drift when warming up. Two control loops of Dee voltage and frequency have been checked. Generator ventilation and its final amplifier structure are improved too. 6) Beam tuning. Beam tuning began at the third quarter of 2007 according to schedule. At first, the ion source and injection line were carefully tested with beam, and then we let the beam enter the inflector. By the end of 2007, beam on the internal target was tested and an essential progress has been made: When beam from ion source is 0.7 mA, and the beam measured at exit of inflector is 0.53 mA, the injection efficiency reaches 75%， Under the conditions of RF occupation ratio of 1/4 and no buncher installed at injection line, the beam inside the machine is successfully passing through the central region. The structure of central region 32 Annual Report of China Institute of Atomic Energy 2007

is shown in Fig. 2. When beam from ion source is 1.0 mA, the beam intensity from different target positions are listed in Table 1.

Fig. 2 Structure of central region

The beam intensities measured at different positions in central region are listed below when the ion source beam is 1.0 mA.

Table 1 Measuring result of beam intensity

Target position Dee viltage/V Beam current/μA Ⅲ 10.2 8.0 Ⅳ 11.2 7.6 Ⅴ 10.5 5.4 Ⅵ 10.5 5.4-5.8

The results clearly show that the beam injected is captured and accelerated eight times by RF field and passes all obstacles of the central region. Based on the results, if the RF buncher is put in the injection line and RF system operates at continuous mode, the beam will increase more then eight times and reach about 50 μA. Meanwhile, if the accelerating Dee voltage and beam intensity from the ion source increase further, the internal beam current will increase consequently. The follow-on tasks, such as optimization of accelerator parameters, fine adjustment of mechanical component dimensions, completion of computer control, internal beam current increasing, beam quality improvement and beam extraction will be finished in the year of 2008.

Analytical Calculations of Chopper for CRM Cyclotron

AN Shi-zhong, ZHANG Tian-jue, WU Long-cheng

A test beam line for pulsed beam generation system for 10 MeV central region model (CRM) compact cyclotron is being constructed at China Institute of Atomic Energy (CIAE). The accepted bunch length with ±3° @ 2.2 MHz or 7 ns is expected by the chopping system. IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 33

1 Single particle’s movement in the chopper Figure 1 shows the structure of the chopper: g is the gap, l is the length of plate, s is the distance between the Chopper and the slit, r is the radius of slit. The waveform used in the chopper is sinusoidal and it will be excited symmetrically with the amplitude of Vm/2 on each plate in anti-phase:

V(t)=Vm/2sin(ωt+φ0)

Fig. 1 Structure of beam chopper

So, solved must be this 2 order differential equation for the movements of particles in the chopper, assuming homogenous sinusoidal deflecting field:

mx =+<< e(/)sin( Vm0c gωϕ t )(0 t t )

tc=l/βc is the transfer time in the chopper.

With vdx/ds=dx/dt and using (x0=0, x0′=0), we can get from above equation:

⎧ eV xl()=+ x x ' l +m ⎡⎤ωϕ t cos − sin( ωϕϕ t + ) + sin ⎪ 002 ⎣⎦ c 0 c 0 0 ⎪ mgω ⎧xl(,ϕ00 )=⋅ aαϕ (, l ) ⎨⎨⇒ eV x'( l ,ϕ )=⋅ bβϕ ( l , ) ⎪ m ⎡⎤⎩ 00 xl'( )=+ x00c0 '⎣⎦ cosϕωϕ − cos( t + ) ⎩⎪ mcgωβ

ec2 V ec 1 V where, a = m ; b = m ;α =−++ϕϕcos sin( ϕϕϕ ) sin ; β =−cos ϕ mc22ω g mc2 βω g c0 c00 0

cos(ϕc0+ϕ ) ; ϕcc==ωtft2π cc. 8 If we choose the following parameters: fc=2.2 MHz, Vm/g=3 kV/cm, c=3×10 m/s, β=0.009 23(E0=40 keV), mc2=939.28 MeV(H－), we have: a=15.23 cm, b=751 mrad (1 rad=10－2 Gy).

2 The analysis calculation for the parameters of the chopper

For a sinusoidal deflecting voltage, particle at –φc/2 initial phase value ends with +φc/2 phase value, receiving no net angular kick, but getting smaller radial displacement. If the wanted pulse length is Δφ after chopper, the particles with initial phase values of –φc/2±Δφ/2 receive either negative or positive angular kicks. These particles around in time shifted bunch center are wanted single bunch for CRM injection. Different φc means different length of chopper plate. Now we calculate the kicks after chopper for the pulse with length of ±3° and the maximum displacement in the chopper. If we choose l=10 cm, pulse length Δφ=6°(±3°), the transition time in the chopper is tc=36 ns or φc=0.499 rad (28.6°), a=15.23 cm & b=751 mrad, then the obtained kicks and displacements after chopper for the bunch center and edge particles are shown in Fig. 2. So, after chopper, the getting net kick for the bunch center is zero and ±20 mrad for the edge particles with the pulse length of Δφ=6°(±3°). The maximal displacement after chopper for the particles is 1.87 cm. 34 Annual Report of China Institute of Atomic Energy 2007

The 4 cm gap is needed and it will lead to the maximal amplitude of sine waveform for the chopper

Vm=12 kV.

Fig. 2 Obtained kicks & displacements after chopper for particles inside pulse with Δφ=6°

3 Simulation for the chopper The chopper is put at the waist focused by EINZEL lens in the injection line. The beam is DC before the chopper, but it will be dependent of the phase values in time after chopper. If the drift between slit and chopper is S=50 cm, the movements of the single particles for bunch center and edge particles with length of Δφ=6°(±3°) are shown in Fig. 3. The size of the slit should be limited as the positions of the edge particles at the slit. So, the particles in the needed pulse will go through the slit, but other parts will be stopped by the slit. It is clear that the particle number will depend on the size of slit. So it is necessary to limit the initial emittance before the chopper.

Fig. 3 Center & edge particles’ movements in pulse with length of Δφ=6°(±3°)

Study of Stripping Efficiency for CYCIAE-100

AN Shi-zhong, GUAN Feng-ping, WEI Su-ming, BI Yuan-jie, ZHONG Jun-qing, ZHANG Tian-jue

A 100 MeV H－ compact cyclotron, CYCIAE-100, is under construction at CIAE and the proton beams will be extracted in dual opposite direction by charge exchange stripping devices[1]. For the IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 35

stripping extraction system in CYCIAE-100, the carbon foil will be used. The production of protons after stripping foil is dependent on the electron loss cross-section. But the electron loss cross-section is dependent on the H－ beam energy. In general, we have the following relation for the electron loss cross-section and velocity: σ∝1/β2, where σ is the electron loss cross-section and β is the relative velocity. From the testing results of Gulley’s and Webber’s (Table 1)[2]，the electron loss cross-section for CYCIAE-100 can be described as the scaling in Table 2.

Table1 Measurements of electron loss cross-section

1018σ/cm2 Electron loss cross-section Webber, Hojvat, 200 MeV Gulley, et al, 800 MeV

σ－，0 1.56±0.14 0.676±0.009

σ0，+ 0.60±0.10 0.264±0.005

σ－，+ －0.08±0.13 0.012±0.006

－ 0 0 + － + Note: where σ－,0: H →H , σ0,+: H →H , σ－,+: H →H

Table 2 Electron loss cross-section for CYCIAE-100

E/MeV γ β σ－,0 σ0,+ σ－,+

70 1.074 598 0.366 087 3.574 400 1.395 930 0.065 295

80 1.085 260 0.388 530 3.173 391 1.239 312 0.056 332

90 1.095 912 0.409 116 2.862 060 1.117 730 0.050 803

100 1.106 560 0.428 180 2.612 880 1.020 420 0.046 380

Table 3 Thickness of carbon foil and stripping efficiency for different energy

Foil thickness / Foil thickness / E/MeV Stripping efficiency/% E/MeV Stripping efficiency/% (μg·cm－2) (μg·cm－2)

100 70 99.854 140 70 99.991

80 99.643 80 99.965

90 99.414 29 90 99.937 8

100 99.045 8 100 99.876 8

120 70 99.964 150 70 99.995

80 99.882 80 99.984

90 99.809 14 90 99.964 5

100 99.657 2 100 99.926 2

So, the stripping efficiency of carbon foil can be estimated as:

η =−1e−Nsσ =− 1e−σ t 36 Annual Report of China Institute of Atomic Energy 2007

23 6.022× 10 −616 Ntts ==×(10 ) 5.02 10 12 N is numbers of atoms per volume, s is distance, t is thickness (unit: μg/cm2). The production of H－, H0, H+ can be estimated as: σ Y 0 =−−,0 [e−−+σσσ0,+−−+x e() ,0 , x ] σσσ−−++,0+− , 0,

Y −1 = e−+()σσ−−+,0 , x Y + =1−Y − −Y 0 x is the numbers of atoms per cm2. The foil thickness and stripping efficiency for CYCIAE-100 can be estimated in Table 3. Fig. 1 shows the production of H－, H0, H+ vs the foil thickness at 100 MeV. For CYCIAE-100, the stripping efficiency is about 99.93% when the carbon foil thickness is 150 µg/cm2. So, the foil thickness of 150 µg/cm2 is enough for CYCIAE-100.

Fig. 1 Production of H－, H0, H+ vs foil thickness at 100 MeV

References: [1] ZHANG Tianjue, et al. A new project of cyclotron based radioactive ion-beam facility. APAC 2004. [2] WEBBER R, HOJVAT C. Measurement of the electron loss cross sections for negative hydrogen ions on carbon at 200 MeV. IEEE, 1979.

Study of Extracted Beam Dispersion for CYCIAE-100

AN Shi-zhong, WEI Su-ming, GUAN Feng-ping, BI Yuan-jie, YAO Hong-juan, ZHONG Jun-qing, ZHANG Tian-jue

A 100 MeV H－compact cyclotron, CYCIAE-100, is under construction at China Institute of Atomic Energy and the proton beams will be extracted in dual opposite direction by charge exchange stripping devices. The dispersion is free inside the cyclotron due to the symmetric magnetic fields. But after the stripping foil, the proton beam will be extracted along the extraction trajectory. Due to the asymmetric magnetic field, the dispersion will be produced and this will lead to the emittance growth in x direction. IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 37

The dispersion from stripping foil to the center of switch magnet (crossing point) will be got from GOBLIN. The position of switch magnet can be assured and the extracted beam parameters will be calculated including the dispersion effects.

1 Dispersion for different switch magnet position Figure 1 and 2 show the dispersions for the energy of 70 MeV and 100 MeV with the switch magnet outside or inside the yoke. The symbol of star in the plots is the position of the switch magnet. The magnetic filed of switch magnet itself is not included. From the results, the dispersion will be large for the lower energy and longer distance. The dispersion for 100 MeV is smaller than the dispersion for 70 MeV at the same position. For the extracted proton beam, the energy spread is about ΔW/W=±0.5%, and the corresponding momentum spread is about δ=Δp/p=±0.25%. For the energy of 70 MeV, the dispersion is 60 cm if the switch magnet is at the position of 2.75 m. So, the produced deviation in x direction due to the dispersion will be: Δx=Dδ=600×0.002 5=1.5 mm and it will be 3 mm for the switch magnet at 3.3 m. So, the dispersion is large if the switch magnet is far from the stripping point. It is helpful for the focusing and matching in post transfer line to put the switch magnet close to the stripping point.

Fig. 1 Position (a) and angle (b) dispersion for switch magnet located at 2.75 m, 100° Solid line—70 MeV; Open line—100 MeV

Fig. 2 Position (a) and angle (b) dispersion for switch magnet located at 3.3 m, 100° Solid line—70 MeV; Open line—100 MeV

2 The dispersion effects including the switch magnet field From above simulation results, it is helpful to put the switch magnet at the position of (2.75 m, 100°). 38 Annual Report of China Institute of Atomic Energy 2007

Fig. 3 and Table 1 show the dispersion for the extracted energy of 70 MeV and 100 MeV including the field of switch magnet. The symbol of star in the plots is the position of the switch magnet and the symbol of triangular is the position of (3.3 m, 107°) after switch magnet along the extraction orbit. The field of switch magnet is different for different extracted energy. From the results, the field of switch magnet can cancel the dispersion for 70 MeV partly, but increase the dispersion for 100 MeV. So the switch magnet is helpful to the low energy, but harmful to the high energy. Therefore, the dispersion must be considered for the post transfer line matching.

Fig. 3 Position (a) and angle (b) dispersion for switch magnet located at 2.75 m, 100° Solid line—70 MeV; Open line—100 MeV

Table1 Dispersion effects for extracted energy of 70 MeV & 100 MeV

Energy /MeV Positions Dispersion 70 100 D/cm 0 0 After foil D′/mrad 0 0 Crossing point at D/cm 57.3 38.2 2.75 m, 100° D′/mrad 265.7 291.5 Position of D/cm 69.4 59.2 3.3 m, 100° D′/mrad 166.9 329.1

Radiation Field Calculation of CYCIAE-100

BI Yuan-jie, ZHANG Tian-jue, JIA Xian-lu, LIU Ping, ZHOU Zheng-he, WANG Feng

For H－ cyclotrons, the H-dissociation during acceleration caused by residual gas and Lorentz stripping can induce some beam losses and result in radioactivity. This is also the case for CYCIAE-100, a 100 MeV compact cyclotron under construction at CIAE. The calculation of prompt radiation fields is used for the local shielding, and the simulation of induced radioactivity which is the source of residual dose equivalent field is to guide the maintenance of the cyclotron.

1 Geometric model The geometric model is shown in Fig. 1. The vacuum tank is made of aluminum alloy LF2 and the material of magnetic yoke is iron. The lost beam bombards the vacuum tank with an angle of 45°; it has a IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 39

uniform distribution from z=－0.5 cm to 0.5 cm and an azimuth-dependent distribution as shown in Fig. 2. The total beam loss is 1.62 microampere. A multi-purpose Monte-Carlo code ‘FLUKA’[1-2] developed by Italian National Institute for Nuclear Physics (INFN) and European Organization for Nuclear Research (CERN) is adopted for the simulation. The build-up and decay of radioactive isotopes is treated with an exact analytical solution of the Bateman equations. Results for production of residuals, their time evolution and residual doses due to their decays can be obtained in the same run. The dedicated database of decay emissions is mostly obtained from NNDC (National Nuclear Data Center).

Fig. 1 Geometric model

Fig. 2 Distribution of beam loss on inner side of vacuum tank

2 Prompt radiation fields The prompt radiation fields are mainly from neutrons and photons. Because the dose equivalent rate of neutron is about 10 times of photon, neutron is the most important radiation for prompt radiation fields. 40 Annual Report of China Institute of Atomic Energy 2007

Fig. 3 shows the contour lines of prompt radiation fields. The prompt radiation field is compared with the MCNP result[3]. The dose equivalent rate calculated by FLUKA is about 189 Sv/h near 45° where having more beam loss and about 25 Sv/h near 30° where having less beam loss, and the results obtained by MCNP is about 143 Sv/h near 45° and about 18 Sv/h near 30° , 20%-30% difference from the FLUKA result.

3 Residual radiation fields The component of cyclotron is activated when bombarded by high-density beam. The induced radioactivity in accelerator components is very likely to be the dominant source of occupational radiation exposure. Fig. 4 shows the contour lines of residual radiation fields at a cooling time of 8 hours. The majority of radioactive species in the vacuum tank at a cooling time of 8 hours are shown in Table 1, and those in magnet yoke are shown in Table 2.

Fig. 3 Contour lines of prompt radiation fields

Fig. 4 Contour lines of residual radiation fields at a cooling time of 8 hours IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 41

Table 1 Majority of radioactive species in vacuum tank at a cooling time of 8 hours

－3 －1 －1 [1] Element Specific activity/(MBq·cm ) T1/2 Γ/((nSv·h ·MBq )@1.0 m)

7Be 221 53.3 d 9.29

18F 274 1.8 h 185

22Na 178 2.6 a 359

24Na 3 200 15 h 512

Table 2 Majority of radioactive species in magnet yoke at a cooling time of 8 hours

－3 －1 －1 [1] Element Specific activity/(MBq·cm ) T1/2 Γ/(nSv·h ·MBq )@1.0 m

48V 1.57 16 d 457.7

51Cr 26.8 27.7 d 6.320

54Mn 13.8 312 d 138.1

52Fe 0.258 8.3 h 139.7

59Fe 0.031 2 44.6 d 178.7

References: [1] FASSO A, FERRARI A, RANFT J, et al. FLUKA: A multi-particle transport code, CERN 2005-10. 2005. [2] FASSO A, FERRARI A, ROESLER S, et al. The physics models of FLUKA: Status and recent developments. Computing in High Energy and Nuclear Physics 2003 Conference. USA, 2003. [3] BI Yuan-jie, LIU Ping, ZHANG Tian-jue. Numerical investigation on radiation dose in vacuum tank of 100 MeV high intensity proton cyclotron. Atomic Energy Science and Technology, 2006, 40(4): 439-442(in Chinese).

Study on Space Charge Effect in Isochronous Cyclotron

BI Yuan-jie, ZHANG Tian-jue, YANG Jian-jun, AN Shi-zhong

As a critical problem to be solved in an isochronous cyclotron, the space charge force will result in the defocusing effect in radial and vertical direction when the beam intensity reaches several milliamperes. It limits the acceptance in vertical direction in classic cyclotron because the vertical focusing force is weak in the central region. However, the longitude space charge effect has drawn more attention in isochronous cyclotron because there is no longitudinal focusing and the strong coupling between the radial and longitudinal motion. The space charge force will evoke a local vortex motion and deform the beam into a spiral as has been noted by several authors. We add space charge force to the code COMA, a linear motion code for Cyclotrons. COMA calculates particle trajectories using transfer matrices, and the effect of space charge force is considered as an integrated kick at the end of every matrix. The transfer step size is changed to 2 degree and a 3D Particle-In-Cell code was developed to calculate the space charge force. At the end of every matrix, we consider the space charge force as follows: ddPqERPqERddEqϕ Rr zz ===,,qREω θ , =− Er dddtmvtmvt00 d t mRω As the energy of particle changes due to space charge effect, it corresponds to a new equilibrium 42 Annual Report of China Institute of Atomic Energy 2007

orbit. A new x, Px due to the euilibrium orbit shifts is xx= +−REO REO new old old new PP=+PREO − PREO xxnew old old new

Figure 1 shows the vortex motion caused by space charge effect. It describes a coasting beam with the emittance of 4 πmm·mrad, phase width of ±6 degree, energy of 1.5 MeV and intensity of 5 milliampere. The number of macro-particles is 15 000. As the rotation speed of the central part of the beam is faster than the outer parts, it forms a core in the center and beam halos outside gradually. The number of spiraling centers is different with the variation of beam length, diameter and density distribution of the charge. Fig. 2 shows the deformation of a beam bunch with phase width of ±12 degree and intensity of 10 mA. It can be seen that two spiraling centers are formed if the diameter of the beam and the charge density distribution is the same as Fig. 1, but the phase width is twice of the case in Fig. 1.

Fig. 1 Vortex motion of short beam bunch due to space charge effect

Fig . 2 Vortex motion of long beam bunch due to space charge effect

IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 43

The strength of space charge effect varies inversely with the momentum, so that its effects are most pronounced in the central regions. The deformation and vortex motion destroy the quality of the beam, but since this mainly occurs at low energy, the situation could be improved by collimating the bad beam at the early stage. The combined effect of both acceleration and space charge force will be taken into account in the follow-on analysis.

Magnetic Measurement for 15-20 mA Ion Source

JIA Xian-lu, ZHANG Tian-jue, YAO Hong-juan, LU Yin-long, LIU Geng-shou

H－ multicusp source is an important ion source which can produce high intensity and qulity beam, and the research on this kind of source will make significant contribution to the development of high intensity cyclotrons at CIAE.

1 Multicusp configuration － H ions in the multicusp are produced by thermal agitation of H atoms or H2 molecules in contact with hot energetic electrons generated by the negative bias of the filament. The most effective method of increasing impact is magnetic field, and all kinds of plasmas will be restricted by magnet field. To advance the density of the plasma on the center axes and to restrict effectively the plasma, we adopt the multicusp structure for the magnets, and the layout of these magnets is shown in Fig. 1.

Fig. 1 Multicusp magnet arrangement

2 Virtual filter The multicusp source consists of two chambers. One is high-temperature chamber and the other is low-temperature extraction chamber. For the former, the high-temperature electrons inside the chamber hit * * H2 to produce the excited state H2 . For the latter, the low temperature 1 eV electrons are attached to the H2 and thus produce H－ ions. The two chambers are connected by a magnetic filter composed of permanent magnets. The filter provides a narrow region of transverse magnetic field (Bmax≈70 Gs) which is strong enough to prevent the energetic primary electrons from entering the extraction chamber to destroy the H－ 44 Annual Report of China Institute of Atomic Energy 2007

ion. Both positive and negative ions, together with cold electrons, are present in the extraction chamber and they form a plasma at very low electron temperature (Te≤1 eV) in the extraction zone. In order to filter the fast electrons, there are water cooled dipole columns near the plasma exit aperture. The H－ multicusp source of CYCIAE-30 used this kind of filter to separate the electron and H－ ion. The principle of this kind of filter is that the magnetic rigidity of electron is much less than that of the H－ ion, so the electron is deflected easily by magnetic field, and as a result the H－ ion can go through the field. The experiment shows that the thin and strong filter is advantageous to the production of H－ ion. Different magnet layout will lead to different virtual filter. At present we use a kind of virtual filter from TRIUMF, which is version E. From the test result of TRIUMF, we can see this kind of method is instrumental to producing H－ ions, and the configuration of version E is shown in Fig. 2.

Fig. 2 Version E virtual filter

3 Meaurement of the magnetic field The consistency of the result from theoretical calculation of the magntic field with that from the test is crucial since it gives considerable influence to beam intensity and quality of the ion source. In general, the key points of the ion source magnetic field concerns two aspects, i.e., consitency of the multcicusp magnetic field and consitency of the virtual filter filed. To test the accuracy of the ion cuap magnetic field, the LZ-610H Tesla meter measure is adopted to measure the magnetic field. 3.1 Measurement on the multicusp field To verify the uniformity of the multicusp magnetic field in a circle, we measure the magnetic field in a circle at different depth, as shown in Fig. 3. From the fiure, we can see that the magnetic field in the neighborhood of z=20 mm is smaller than other depth, because it is near the entrance where the leakage takes place. There are some differences between thoery calculation and measured magentic field, which are caused by the machining and installation of the magnet. We also can see that the difference of the magnetic field is no more than 20 percent. Such a difference is due to the non-consistency of the added magnetic field and the difference in the way to measure the magnetic field. However, the magnetic field uniformity of this type satisfies the need of the ion source. 3.2 Measurement on the virtual filter field In order to verify the accuracy of the theoretical calculation for the magetic field, the virtual filter field is measured along the center axis, and the result is shown in Fig. 4. From the figure, we can see there IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 45

is little difference between theoretic and measurement results. Due to the fact that the real magnet set up in the lens is a little bigger in dimension than that applied in the theoretic calculation, the real magnetic field is smaller than calculated value. In addition, the fabrication tolerance can not be avoided, which will directly result in some difference. In spite of that, this will not bring much influence to the beam of the ion source.

Fig. 3 Multicusp magnetic field ◆—Measuring value，z=20 mm；■—calculating value，z=90 mm；▲—Measuring value，z=90 mm

Fig. 4 Result of virtual filter field ■—Measuring result；Solid line—Theory result

Design of 15-20 mA H－ Cusp Source

JIA Xian-lu, ZHANG Tian-jue, LU Yin-long, YAO Hong-juan, CHEN Rong-fan, ZHONG Jun-qing, SONG Guo-fang, LIN Jun

Cusp source is one of the essential elements in the high density cyclotron, whose properties have a great impact on the extracted beam of the cyclotron. The article introduces the design and machining of 46 Annual Report of China Institute of Atomic Energy 2007

the H－ cusp source applied to the high intensity proton beam cyclotron. By investigating deeply into the technology of high intensity plasma production, long life DC filament emission of electrons, magnetic confinement, electron filtering, residual gas and electron extraction control, we designed a new cusp source with an average beam density of 15-20 mA based on the 10 mA H－ cusp source at CIAE.

1 Introduction The beam intensity and quality of the ion source is an important factor that confines the development of the intense proton cyclotron. To improve the beam intensity and quality, CIAE has been devoted to the improvement of ion source. In 2000, an ion source was built at CIAE with an average beam intensity of 5.2 mA and beam emittance of 0.65 πmm·mrad[1]. In 2004, we built an H－ ion source with a beam density higher than 10 mA. In order to improve the beam density and to satisfy the need of the upgrade project of the Beijing Tandem Laboratory at CIAE, we will build a new ion source based on the 10 mA one, producing 15-20 mA beam.

2 Configuration of the ion source Figure 1 shows the configuration of the H－ ion source. The source assembly consists of a tubular plasma chamber (inner diameter: 98 mm; length: 152 mm) with ten columns of permanent magnets (Nd-Fe-B material) to provide a multicusp field and serves as a virtual filter, a three electrode extraction system, a top cover with a confinement magnet inside. In the extraction system, there is a pair of small permanent magnets embedded in the extractor for electron filtration and a compact electric magnet ring enclosed on the ground electrode for x-y steering of the beam. The ion source adopts double filament, which proves to be better than single filament through the experiment.

Fig. 1 Configuration of H－ ion source

3 Configuration of the magnetic field for ion source The detailed description on the configuration of the source magnetic field is indicated in the Ref. [2], so we skip over this part here.

4 Design of the extracted electrode The electrode of the ion source includes plasma electrode, lens and ground. The following formula IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 47

was used initially in choosing initial values for certain parameters such as the extraction gap d, radius rc of the aperture in the first extraction electrode (cathode), and extraction voltage V for space charge limited flow through the system[3]: 3/2 I=Pp(1－1.6d/rc)V 1/2 2 2 Pp=4/9·ε0(2q/M) πa /d In the equation, q is the charge, M the mass of the ion, and a is radius of the extraction aperture. Based on the theory, we design a three-electrode extraction configuration, as shown in Fig. 2. From the Fig. 2, we can see that the voltage V1 is determined by the injection energy, and the extraction voltage V2 is determined by V1, g1, plasma voltage and arc voltage and etc. The extraction configuration is calculated by code IGUN. We can get the most desirable result by matching the seven geometrical parameters of the electrode, gap of the apertures and gap between the electrodes. Based on the requirement for our system, two ion source extraction configurations have been designed. One is 28 keV for debug ion source, and the other is 40 keV for injection line of the cyclotron. 4.1 28 kV configuration

When the extracted beam is 21 mA and energy is 28 kV, the parameters are set as V1=28 kV, V2=3.8 kV, D1=13 mm, D2=10 mm, D3=14 mm, g1=2.5 mm, g2=11 mm. The simulation of beam optical property is shown in Fig. 3 and Fig. 4. From the results we can see that the beam density is 20 mA，and the 70% normalized emittance is 0.605 πmm·mrad.

Fig. 2 Extraction configurations

Fig. 3 IGUN simulate 28 kV extraction configurations

4.2 40 kV configuration

When the extracted beam is 21 mA and energy is 40 kV, the parameters are set as V1=40 kV, V2=5.5 48 Annual Report of China Institute of Atomic Energy 2007

kV, D1=13 mm, D2=10 mm, D3=16 mm, g1=2.5 mm, g2=11 mm. From the results we can get that the beam density is 20 mA and the energy of the beam is 40 keV.

5 Conclusion Till now we have finished the fabrication of the ion source, and the primary components and the auxiliary facilities have been installed and tested. The vacuum has reached 5.7×10－5 Pa after the test. The high voltage insulation test has been finished, and it turns out that the leakage current is 1mA at 40 kV, which meets the requirement for the test. Besides, the power supply has been ready for the beam test. After initial test, we can get 1.5 mA H－ from the ion source.

References: [1] ZHANG Tianjue, et al. Review of Scientific Instruments, 2004, 30(5). [2] JIA Xianlu et al. Annual Report of Chinese Institute of Atomic Energy. Beijing: Atomic Energy Press, 2006. [3] ALTON G D. Applied Atomic Collision Physics. New York, 1983: 163.

Three Methods and Comparison for Vertical Acceptance Calculation of CYCIAE-100

YAO Hong-juan, ZHANG Tian-jue, GUAN Feng-ping, LU Yin-long,

The matching calculation of the beam emittance is very important in the central region design of a cyclotron. The reason is that the emittance matching will affect directly the beam loss that occurs during acceleration and exert influence on extraction beam qualities as well. The focusing in central region depends on RF phase. Therefore the initial emittance which is required to minimize the vertical envelope in the cyclotron is the function of RF phase. The acceptance of the central region will be provided to injection line and inflector design as the fitting conditions. We studied the vertical acceptance for the CYCIAE-100 cyclotron, using numerical methods and semi-analytical method respectively, and compared the results for these different methods.

1 Method #1 From particle tracking results by CYCLONE from injection point to a certain energy where the value of υz varies slowly, vertical envelope data were obtained and can be used to get transfer matrix RN and

RN+1 , corresponding to matrix from injection point to turn number of N and N+1. Then transfer matrix M from turn number N to (N+1) is got in the following formula:

−1 MRR= NN+1 (1)

Based on the beam transport knowledge, the twins parameters of the eigen-ellipse will be calculated: ⎧ M − M 2 α = 11 22 ⎧ MM+ ⎪ ⎪ ⎛⎞11 22 ≥ 2sinμ sinμ =− 1⎜⎟ ,M12 0 ⎪ ⎪ ⎝⎠2 ⎪ M (2) ⎨ ⎨β = 12 ⎪ 2 sin μ ⎛⎞MM11+ 22 ⎪ ⎪sinμ =− 1 −⎜⎟ ,M12 < 0 ⎪ 2 −M 21 ⎩ ⎝⎠ ⎪γ = ⎩ sin μ IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 49

T The sigma matrix at the injection point can be derived and according to σ=Rσ0R , the sigma matrix at －1 T －1 the injection point is σ0=RN σ(RN ) , then the phase space ellipse is described, i.e. corresponding to the acceptance of a certain RF phase. We calculated the vertical acceptances for three initial RF phases: Phi0, Phi0－20, Phi0+20; the normalized emittance of 2 πmm·mrad was used, particle tracking to the turn 78, where the reference particle energy is 17.6 MeV. Fig. 1 demonstrates the vertical acceptance calculation results for three different RF phases; the overlap area is the acceptance emittance for the 40° phase width.

2 Method #2

Starting from the injection point, we selected a number of particles (with different z and Pz) in vertical phase space，the coordinates of the central particle was chosen in the radial direction, tracked forwards starting from injection point with 40 keV to high energy. Then we checked whether the particles were inside the static ellipse or not. Limited by the data number, the particles were tracked to the turn 6, corresponding to the energy of 1.443 MeV, α=0.000 00, β=2.265 61, γ=0.441 382 2, the normalized emittance of 0.5 πmm·mrad was used. The results for 40° phase width are shown in Fig. 2.

Fig. 1 Vertical acceptance calcualted by method #1

Fig. 2 Vertical acceptance calcualted by method #2 ◆—Phi0；■—Phi0－20；▲—Phi0+20

50 Annual Report of China Institute of Atomic Energy 2007

3 Method #3 We tracked 8 particles from the static ellipse (0.5 πmm·mrad) backwards from a certain high energy (17.6 MeV, corresponding to the turn of 78), up to the injection point, and then got the accepted ellipse at injection, did the same for different phases. The eigen-ellipse at high energy was obtained by two methods: one is by computer code CYCLOP and the other is the result from the matrix method. The result is shown in Fig. 3.

4 Comparison and conclusion To compare the three methods introduced above, we tracked particles for 6 turns by taking a normalized emittance of 0.5 πmm·mrad. The result is shown in Fig. 4. We can see that the results from the three methods are very close, especially for the results by method #2 and #3 which are almost identical to each other; the notable difference between #1 and #2, #3 appears only for the case of Phi0+20. From the comparison above, compared to method #1 which is semi-numerical and semi-analytical, the results from method #2 and #3 have a high accuracy. From the perspective of complexity, method #2 is not a good choice because of the huge particles and the complicate after-treatment. Comprehensively speaking, method #3 tops the other two for the vertical acceptance calculation of central region due to its reliability in result and simplicity in practice.

Fig. 3 Vertical acceptance calculated by method #3 Initial eigen-ellips were obtaind by CYCLOP and matrix method respectively

◆—CYCLOP_Phi0; ■—CYCLOP_Phi0－20; ▲—CYCLOP_Phi0+20; ×—Matrix_Phi0; *—Matrix_Phi－20; ●—Matrix_Phi0+20

Fig. 4 Comparison of vertical acceptances by 3 methods ◆—#1_Phi0; ■—#1_Phi0－20; ▲—#1_Phi0+20; ◊—#2_Phi0; *—#2_Phi0－20;

●—#2_Phi0+20; +—#3_Phi0; ▄—#3_Phi0－20; □—#3_Phi0+20 IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 51

Analytical Calculation for Fringe Field of Spiral Inflector

YAO Hong-juan, ZHANG Tian-jue, JIA Xian-lu

The inflector is a transmission element which deflects the beam by 90° using the electric field between the electrodes. For the design of the spiral inflector, it is important to find a proper analytical formula for the fringe field at the entrance and exit of the inflector. An approximate formula was used in the program CASINO for the analytical calculation for the fringe field, here we calculated the electric field through a numerical method, then the formula was obtained by fitting for the field map and the interpretation was provided.

1 Analytic formula used in CASINO CASINO makes a simplified assumption that the fringe field is one dimension and lies solely in the ur direction. The analytic formula used is

E=Ecr(1+tanh(－z－(－zinf－δ)/spacing)α)/2 (1) δ=spacing(0.37－e－2.5r), α=1.15+0.2/r2 (2) Where r is selected to 1 (because the program INFLECTOR sets d=g), ‘spacing’ is an input parameter, means the half size of the gap between the electrodes.

2 Interpretation for the formula As shown in Fig.1, defining r=d/g, we calculated the electric field for this geometry, setting half gap g=4 mm, the length of the electrode is 10 mm, the r value is selected to 1, 1.5, 2, 3 and 4 respectively. RELAX3D was run to calculate electrical potential distribution, the mesh size was 0.1 mm, the potential map is shown in Fig. 2, r=1 and r=4 as examples.

Fig. 1 Geometry used to define fringe field at entrance and exit of inflector

For the output of RELAX3D, we defined j=int(Jmax/2)+1, f=V(j+1)－V(j－1), and

zp=(－10+(i－1)×0.1)/g=(－10+(i－1)×0.1)/4 (3) The formula fitting was done for the value of f, then

f=－0.025(1－tanh(zp－fudge)scale) (4)

The result is shown in Fig. 3, the abscissa is zp and the ordinate is f; the plots are from the data directly from RELAX3D and the formula results by (4), we can see that they are almost coincident, which 52 Annual Report of China Institute of Atomic Energy 2007

means this analytic formula got by fitting can well describe the realistic potential distribution. The fitted parameters are given in Table 1.

a b

Fig. 2 Potential plot by RELAX3D for r=1 (a) and r=4 (b)

Fig. 3 Potential data comparison between RELAX3D and formula

Table 1 Two fitted parameters in formula (4)

r=d/g fudge scale 1 0.29 1.35 1.5 0.35 1.24 2 0.37 1.19 3 0.37 1.16 4 0.37 1.16

The two parameters in Table 1 were fitted as the functions of the r, the formulas are the following:

fudge=0.37－e－2.5r, scale=1.15+0.2/r2 (5) The results between formula (5) and Table 1 were compared; we can see that the difference increases with the r value. Formula (4) and (5) obtained by fitting is exactly formula used in CASINO. The electric field distribution calculated by CASINO using analytic formula is well agreeable with the results from RELAX3D.

IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 53

Influence of Radial Field on Emittance in Median Plane at CYCIAE-100

ZHONG Jun-qing, AN Shi-zhong, YAO Hong-juan, BI Yuan-jie, ZHANG Tian-jue

If the mirror symmetry of poles in cyclotron is violated, the radial component of the field would appear in the median plane. The radial field can induce the shift of orbit centre in vertical orientation, and this shift will induce a beam blowup at relevant vertical resonances. The equation[1] of motion for z in case of a Br is given by

2 d z 2 r0 2 +=ν zrzB (1) dθ Bz

Where r0 is the nominal radius, vz is the vertical resonance and Bz the average field. We can write the radial field as a Fourier series in calculation, ∞

Brrk=cos∑ Bkθ k=0 So the relation between one of the Fourier components and the vertical motion will be expressed by

d2 z r +=ν 2 zBk0 cos θ (2) dθ 2 zrkB

The general solution of this equation is

⋅ z' 0 r B 0 rk (3) z(θ ) = z 0 cos ν zθ + sin ν zθ + 2 2 [cos kθ − cos ν zθ ] ν z B z (ν z − k ) ∂z Where z and z' are initial position and velocity of centre particle ( ) respectively. 0 0 ∂θ θ =0

1 Uniform distribution of radial field Br

We assume that, initially, the centre particle is in the median plane of CYCIAE-100, i.e. z0= z'0 =0. Simultaneously, we assume the radial field Br is uniformly distributed in median plane at 2 Gauss, i.e., the k=0 in formula (3). We can obtain the relation between the shift of orbit centre in vertical and the rotation angle from the expressions and COMA code[2]. In this part, we calculate and simulate the shift of the particle whose energy is 60.4 MeV, then, the vertical resonance and the average radius are 0.645 44 and 147.2 centimeters respectively. The results of shift from formula and COMA code are shown in Fig. 1. We will find that the result from formula is identical with that from COMA. In order to calculate the influence of radial field on emittance, we assume the initial emittance of beam is 2 πmm·mrad, and then the position of centre particle in phase space is shown in Fig. 2, meanwhile the initial emittance and circulating emittance is shown in Fig. 3. The value of circulating emittance is 3.14 πmm·mrad and the ratio of the emittance growth is 57%. According to the relation between the emittance growth and the shift of centre particle, Δz=(f 1/2－1)z (4) We will get the shift Δz=0.92 mm. However, after rotated for 31 turns, the average shift of the centre particle is 0.92 mm at initial position i.e., θ=0° in cyclotron. So when there is uniform radial field in median plane, the circulating emittance growth can be expressed by: 54 Annual Report of China Institute of Atomic Energy 2007

n 1 rB0 r z (1 cos 360zk ) （5） Δ=∑ 2 − ν nBk=1 ν z Δz 2 （ ） ε c = ε 0 (1 + ) 6 z 0

Where n is rotation turns, and ε0 is initial emittance.

Fig. 1 Vertical shift of centre particle Solid line—Result from formula; ●—Result from COMA

Fig. 2 Position of centre particle with rotated turns

2 First Harmonic distribution In this part, we will consider the influence of the first harmonic radial field on the emittanc, and we assume that the radial field Br=2cos θ, and the energy of the particle is 60.4 MeV. Then the average vertical shift of the centre particle will be derived from the formulas (3) and (5), 1 n rB Δ=zkk01r [cos360 − cos(360ν )] =− 0.668 mm ∑ 2 z nBk =1 (1)ν z −

when we assume the initial emittance is 2 πmm·mrad, the circulating emittance is 2.792 πmm·mrad, and the ratio of emittance growth is about 39.6%, the vertical shift of particle derived from formula (4) is －0.668 mm. The vertical shift of the centre particle is shown in Fig. 4, and the circulating emittance and initial emittance are shown in Fig. 5. IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 55

Fig. 3 Circulating emittance and initial emittance 1—Initial emittance; 2—The 3rd turn emittance; 3—The 11th turn emittance;

4—The 13th turn emittance; 5—The 22nd turn emittance; 6—The circulating emittance

Fig. 4 Vertical shift of centre particle in 0° angle

Fig. 5 Circulating emittance and initial emittance 1—Initial emittance; 2—The 6th turn emittance; 3—The 19th turn emittance;

4—The 25th turn emittance; 5—The 29th turn emittance; 6—The circulating emittance

According the results derived from COMA code, we found that the circulating emittance and the 56 Annual Report of China Institute of Atomic Energy 2007

vertical shift were 3.287 πmm·mrad and 1.03 mm respectively when the phase of the 1st harmonic was 270° or 90°.

3 Conclusion The energy is higher and the ratio of emittance growth is bigger, when the initial emittance and radial field components Br are given. So, if the ratio of emittance growth is kept less than 50% with the initial emittance of 2 πmm·mrad, the uniform radial field components will be kept less than 1.5 Gauss at highest energy, and the amplitude of the 1st harmonic is less than 1.9 Gauss. Moreover we should pay more attention to the phase of the 1st harmonic during the shimming, i.e. to avoid the phase of 270° or 90°.

References: [1] KLEEVEN W. The influence of magnetic field imperfections on the transverse orbit behavior in the TR30 H－ cyclotron, TR30-DN-15. 1988. [2] KOST C J, MACKENZIE G H. COMA—A linear motion code for cyclotrons. IEEE Transactions on Nuclear Science, 1975, NS-22(3).

Influence of Non-uniform Conductance of Main Magnet on Median Plane Field in CYCIAE-100

ZHONG Jun-qing, ZHANG Tian-jue

In order to achieve good beam quality, the amplitude of 1st harmonic field will be limited to less than 2 Gauss in CYCIAE-100. Many factors will give impact on the magnetic conductance of the magnet, including chemical composition, inner crystalloid size and the heat treatment process of the magnet. The fact is that the un-uniformity of all the factors can not be avoided during the forging and casting of raw and processed materials. Consequently the non-uniform magnetic conductance conduced by the factors will bring the imperfection field in median plane. The relationship between the variety of magnetic conductance and the magnetic field in median plane can be expressed below[1]:

BB ∫∫airddllNI+= Iron airμμ0Iron Iron

Approximately,

BIronμ 0 BNILair =−() μIron δ

There, δ is gap height between poles, L is length of route field pass, Bair is intensity of magnetic induction in gap, BIron is intensity of magnetic induction in magnet, μIron is the magnetic conductance of the magnet,

μ0 is the magnetic conductance of air. In order to get the relationship between non-uniformity of magnetic conductance and the field in median plane at CYCIAE-100, we simulated the field in median plane using FFE code. 1) The influence on median plane field conduced by non-uniform magnetic conductance in poles Because the influence on field conduced by no-uniform magnetic conductance is not partial influence but entire influence, while conducting the simulation, we assume that the magnetic conductance of one pair of the poles is different from the other three pairs of poles which are of the same conductance. In the mean IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 57

time, there is no difference in the uniformity of conductance for the top/bottom yokes and return yokes. During the simulating calculation, the top/bottom and return yokes applied the conductance of ANSI1008 steel at room temperature. The conductance and deflection of conductance are shown in Table 1.

Table 1 Conductance and deviation of conductance

H/(A·m－1) 104μ/(H·m－1) 104Δμ/(H·m－1) H/(A·m－1) 104μ/(H·m－1) 104Δμ/(H·m－1)

109.8 91.07 0.91 8 352.7 2.15 0.021 5

174.8 74.37 0.744 20 440.1 1.00 0.01

492.8 30.44 0.304 23 230.3 0.90 0.009

4 375.1 3.89 0.038 9 116 945.1 0.2 0.002

The results from simulation are shown in Figs. 1-3 respectively. From those figures, we can see that deviation of magnetic conductance will bring the 1st harmonic field in the median plane, and the amplitude will be larger in large radius than that in small radius. When the deviation of magnetic conductance is 1%, the intensity of magnetic induction in poles is from 1.0 T to 1.8 T, and the amplitude of 1st Harmonic is less than 8 Gauss.

Fig. 1 Magnetic distribution in radius 100 cm

Fig. 2 Magnetic distribution in radius 180 cm 58 Annual Report of China Institute of Atomic Energy 2007

Fig. 3 1st Harmonic field in radius100 cm and 180 cm Solid line—R=100 cm；Open line—R=180 cm

2) The influence on median plane field conduced by non-uniform magnetic conductance for top/bottom yokes The top/bottom yokes will adopt an integral structure in CYCIAE-100. In order to simulate the influence of the no-uniform conductance, we assume 1/4 of the top/bottom yoke is A3 steel, Q235 and DT4 in different calculation, but the remaining 3/4 of the yoke is ANSI1008 steel. The magnetic conductance of A3 steel, Q235 and DT4 is shown in Table 2.

Table 2 Magnetic conductance of A3 steel, Q235 and DT4

－1 4 －1 4 －1 4 －1 H/(A·m ) 10 μA3/(H·m ) 10 μQ235/(H·m ) 10 μDT4/(H·m ) 500 16 23.6 29 1 000 11.6 13.9 15.6 2 500 6.04 6.12 6.68 5 000 3.34 3.34 3.52 10 000 1.81 1.78 1.88 20 000 0.98 0.94 1.00 30 000 0.67 0.65 0.70 40 000 0.50 0.495 0.55 50 000 0.40 0.40 0.45

Fig. 4 1st harmonic field in radius 100 cm IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 59

The results from simulation are shown in Figs. 4-6 respectively. From those figures, we can conclude that the deviation of magnetic conductance in top/bottom yokes will bring the 1st harmonic field in the median plane. Simultaneously, the distribution of field will be heavily affected. The fact is that the smaller the deviation is, the smaller the 1st harmonic is. In the same condition, the amplitude change of the 1st harmonic field is not notable along with radius variation.

Fig. 5 1st harmonic field in radius 180 cm

Fig. 6 Magnetic distribution in radius 180 cm

Reference: [1] ZHAO Kaihua, CHEN Ximou. Electromagnetism: Second Edition. Publishing Company of High Education, 1996: 612-620.

Test and Analysis on Multipactoring Phenomenon in 70 MHz RF System of CRM Cyclotron

XIA Le, ZHANG Tian-jue, JI Bin, ZHAO Zhen-lu, YIN Zhi-guo

The multipactoring phenomenon takes place in almost all RF cavities. In some areas, where the resonant conditions are fulfilled, it turns to a chain multiplication of electron current generated by impact of primaries and emission of secondary electron emission. 60 Annual Report of China Institute of Atomic Energy 2007

1 Experimental results All experiments are taken under the vacuum (about 10－6 mbar) and magnetic field condition. Before inputting the RF signal with signal generator, we usually record the S11 parameter of RF cavity from the inputting port with network analyzer first, and then figure out the rough resonance frequency of the system. Signal generator (outside the RF transmitter) inputs small signal on the previous frequency replacing the original signal generation circuit, so we can adjust the amplitude conveniently. The output signal is in 10:1 pulse mode when the input signal is quite small at first, with rising of input signal, the duty ratio extends from 10% to 100% (CW). The feedback signal was got from the coupling loop in the transmitter, and the signal captured by oscillograph was from the lower pick-up port of the cavity with a 10 dBm attenuator. The input port of oscillograph was set to 50 Ohm impedance mode. 1) Set the input signal to 70.940 MHz, 11 dBm. 2) Raise the amplitude to 11.46 dBm, the amplitude of pulse signal rose to 11.9 mV, the frequency of pulse was about 2 kHz. 3) Continue pushing up the amplitude to 12.06 dBm, there was a different pulse signal present. The amplitude of the new one was about 910 mV. The width was equal to the small pulse, and the distribution of the big/small pulse was ransom (Fig. 1).

Fig. 1 Output signal captured by oscillogragh when 2 pulse signals both present

4) Keep pushing up the amplitude, and the width of big pulse signal and the small one were both extended. Then two different cases are likely to occur. In one case, the signal was converted to CW at the amplitude of small one’s (the input signal from signal generator was about 12.32 dBm, the amplitude of pick-up signal was about 40 mV). In the other case, the signal was converted to CW at the amplitude of big one’s (The input signal from signal generator was about 12.34 dBm, the amplitude of pick-up signal was about 1 V). 5) After being CW, the amplitude would change between small and big one randomly. The experimental results of pulse-CW changing process are listed in Table 1. IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 61

Table 1 Experimental results of pulse-CW changing process Output power Reflected power Solid Cavity Signal frequency Signal amplitude Cathode Screen read from power read from power state pick-up of generator/MHz of generator/dBm current/A current/mA meter/kW meter/kW current/A signal/V 70.927 12 0.85 38 4 0.4 2.6 1.4

70.910 12.84 0.65 150 5.1 0.7 4.3 0.970

70.920 － 0.58 130 5.2 0.7 4.2 0.790

70.930 － 0.55 130 5.2 0.7 4.2 0.730

70.940 － 0.52 98 5.1 0.75 4.2 0.620

70.945 － 0.53 97 5.1 0.75 4.2 0.580

2 Theoretic analysis When the electron collides with the surface, two phenomena take place: secondary emission and back-scattering. The number of secondary electrons is calculated using following procedure. If acts of emission of secondary electrons are supposed to be independent on each other, the process of emission can be described in term of Bernulli model of random processes and then the probability of emission of n electrons is:

(Fδ ) n P = exp −Fδ （1） n n! where δ is the value of secondary emission coefficient for each collision, i.e. for the energy and the angle of the arrival electron, and F is the enhancement factor, which depends on the material and the condition of the surface. To determine the number of secondary electrons, a random number x from the range [0, 1] is compared with value:

k ,… （ ） xkn= ∑ P k=0,1,2 2 n=0

If x more than xk−1 and less than xk, k is supposed to be the number of secondary electrons for this collision. The energy and angular distributions of secondary electrons are different for each type of material. Using those distributions, two equations are solved, to get the energy and the angle of each secondary electron:

E2 FEE()d = x （3） ∫ EE 0

Θ2 Fx()dΘΘ= （4） ∫ Θ Θ 0

Where, E2 is the energy of the secondary electron; Θ2 is the angle between the secondary electron velocity vector and the normal vector to the surface in the point of collision; FE (E) and FΘ ()Θ are the energy and angular distribution of secondary electrons; xE and xΘ are random numbers from the range [0, 1]. From the previous analysis, the area where the secondary electron emissions take place is related to a Dee-plate voltage distributing in a certain range with blur limits. The experimental result can be used to 62 Annual Report of China Institute of Atomic Energy 2007 verify it. However, in order to get over multipactoring completely, the essential method still lies on long time and continuous conditioning.

PFD Design and Simulation Based on FPGA

YIN Zhi-guo, ANTONINO Caruso1, ANTONINO Amato1 (1 INFN-Laboratori Nazionali del Sud)

The detector has two D-flee flop cells, and three state, signal A and B transitions will trigger PFD to change its state, often referred as Lag-state, Lead-state and Equal-state. Each state has its own output vector, which works together to give the DC mean level proportional to input phase differences at same input frequency and will give ramping up or down respect to frequency lead or lag.

1 Digital PFD FPGA implementation Inside FPGA the F and G function generator introduced delay can not be neglected. However, with a given FPGA IC, one can not reduce this item. Therefore logic map and packing are more important in this case. The strategy is to control the clock source to the corresponding output in a symmetric manner, thus the side-effect caused delay can be minimized. Different type and version of synthesize tools were used to get perfect symmetric logic translation and packing result, whose procedure is summarized below.

Table 1 Different synthesize tools and its result

Tool Target Design input Recourses cost Symmetric

ISE9.1+XST XC3S200 Schematics 4 Slices No

ISE9.1+Synplify Pro XC3S200 VHDL 4 Slices No

ISE8.2+XST XC3S200 Schematics 4 Slices Yes

ISE8.2+Synplify Pro XC3S200 VHDL 4 Slices Yes

ISE F3.1i XC4000 Schematics 2 Slices Yes

After comparing the result generated by different tools, the design is fixed by direct packing related logic into 4 look up tables with carefully consideration about symmetry. The related schematic is shown below. In order to fix the design, instead of allowing the design floating each time with different logic packing methods, all logic in Fig.1 was directly packet with VHDL LUT sub-description, e.g. Look up table is packet with: ‘INIT => not(not(not(not I1 and not I2) and I0)and not (I3 and not(not I2 and I1)))’.

2 Design simulation and sensitivity 1) POST-MAP simulation The simulation was done with two 45 MHz inputs with positive and negative 1.8 degree phase difference. Following formula was used in this procedure:

PWUp− PW Down VVout=⋅ OD (1) PW45 MHz IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 63

In which, VOD is the driven voltage. As in most cases, LVCOMS 33 IO standards were adopted for FPGA input output, the output voltage can be calculated by setting VOD=3.3 V. The PW45 MHz is 22.22 ns, as the simulation adopts 45 MHz working frequency. The PWUp and PWDown can be obtained from the simulation. The calculated voltage response is shown in Fig. 2 as ‘PostMAP’ item.

Fig. 1 Digital PFD implementation

2) PAR issue and POST-PAR simulation With proper VHDL coding, the synthesize procedure is bypassed. In this circumstance, physical layout becomes the key issue to make a high performance PFD inside FPGA. According to Fig. 1, the design occupies 4 IOB and 2 SLICE resources inside Spartan 3 FPGA. Various placement and simulation had been conducted to evaluate the performance, and part of placement and simulation results are listed below, which suggests that in the best condition the PFD has 12 Pico second pulse width mismatch as detector offset. Another interesting thing found by PAR and simulation is the fact that the phase detector gain more sensitivity due to non ideal internal connection, when two inputs are almost in phase. This will benefit phase loop control, because in normal operation the phase loop will always work at in-phase inputs. The sensitivity that increases here will bring extra gain to the loop, consequently suppress phase noise better at working point. The boost and simulation result is shown in Fig. 2 (Curve HH54 and HH69 are refer to the 1st and the 2nd item in Table 2).

Fig. 2 POST-PAR simulation and sensitivity boot Dot line—HH54; Open line—HH69; Solid line—POSTMAP 64 Annual Report of China Institute of Atomic Energy 2007

Table 2 List of placement and simulation result

IOB placement SLICE placement Post PAR simulation (best Cond.)

F1 F2 Down Up S1(N_35) S2(N_36) Down Up Difference

"T8" "R9" "T7" "P9" X18Y1 X18Y0 1 578 ps 1 566 ps 12 ps

"T8" "R9" "R7" "P9" X18Y1 X18Y0 1 543 ps 1 869 ps 326 ps

"T8" "R9" "R7" "P9" X18Y0 X18Y1 2 527 ps 2 271 ps 256 ps

"T8" "R9" "M7" "P7" X14Y1 X14Y0 1 617 ps 1 862 ps 245 ps

"N8" "P8" "M7" "N7" X14Y1 X14Y0 1 732 ps 2 019 ps 287 ps

According to the simulation result, the sensitivity is : VV− S 45 MHz = +°1.8 −° 1.8 =°18.333 mV /( ) (1) PFD 3.6°

Power Loss on Cavity of CYCIAE-100

JI Bin, ZHAO Zhen-lu, ZHANG Tian-jue, XIA Le, YIN Zhi-guo, WEI Su-min

The resonant cavity is an important part of the RF system for CYCIAE-100, which functions to supply steady RF power to accelerate the ion. The hot distortion by the RF power is one of the dominating reasons that impede the performance of the cavity. As a result, the water cooling system layout of the cavity is crucial and the power loss simulation of the cavity is of primary importance to provide the data to the water cooling system design. The resonant cavity is designed and optimized using CST MICROWAVE STUDIO, from which we obtain that the resonant frequency of the cavity is 44.5 MHz, and the unloaded Q value is approximately 10 300. The voltage at the central region is 60 kV and at the large radius area is 120 kV, i.e., the ration is about 1:2. All these data meet the design requirement. The principal structural parameters of the cavity are shown in Table 1, and the power loss of the cavity is shown in Fig. 1.

Table 1 Principal structural parameters of cavity Outer conductor Inner conductor Height Outer radius Angle Stem1 Stem2 Length of dee plate Angle of dee plate 1.26 m 1.98 m 36.6° 6.4 cm 7 cm 1.86 m 34.4°

Fig. 1 Schematic diagram of power loss on cavity IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 65

The power loss can be calculated using the expression:

1 πμ f 2 PS= H ∂ (1) W 2 σ ∫

Where μ=4×π×10－7 H/m，f=4.45×107 Hz，σ=5.8×107 S/m, H is from the simulation. The cavity is separated into several parts in the power loss calculation, as shown in Table 2. The total power loss of the cavity is about 28 kW. From the result of the calculation, we can see that the power loss of the outer conductor, the short plate, the Dee and the two stems is comparatively apparent, and thus more attention should be paid there when the picture of the water cooling is not so clear. Theoretically, the unloaded Q value is about 10 300, while in the engineering, it will be lower due to the influence of the factors such as the processing procession and surface finish quality of the metal cavity. When the unloaded Q value reduces from 10 300 to 6 000, the total power loss of the cavity will increase from 28 kW to 48 kW. Meanwhile, the power loss for each part will subsequently increase in proportion.

Table 2 Power loss of cavity Structure Loss/W Percentage/% Structure Loss/W Percentage/% Outer conductor 5 235.0 18.5 Stem1 6 534.0 23.1 Short plate 3 327.7 11.7 Stem2 5 380.0 19.0 Dee 7 198.0 25.4 Coupling capacity 20.5 0.1 RF liner 668.0 2.4 Tuning capacity 61.8 0.2

Through integral calculation on the magnetic vectors of each part of the cavity, we have obtained the desired power loss distribution at each location, paving the way for the ongoing design of the water cooling system.

References： [1] ACERBI E，SORBI M，et al. Design of the RF cavity for a 200 MeV proton superconducting cyclotron. Proc. 14th Int. Conf. on Cyclotrons and Their Applications 1995:245-248. [2] WANG Xiulong, et al. The Alternative of RF System Design for the 100 MeV Cyclotron at CIAE. Proc. of CARRI 2006 and NIM-B. [3] JI Bin, et al. Theoretical and practical study on RF model cavity of 100 MeV H－ cyclotron. Chinese Physics C, 2008, Supplement: 32.

Vertical Focusing Enhancement Through Asymmetric Shimming Method for CYCIAE-100

WANG Chuan, ZHANG Tian-jue, YAO Hong-juan, ZHONG Jun-qing

Apart from the Thomas force in a sector cyclotron, the spiral sector configuration shown in Fig. 1 could provide two extra vertical focusing forces, i.e., the Kerst force and the Laslett force. In this configuration, the relation between vertical oscillation frequency vz and spiral angle v can be expressed as 66 Annual Report of China Institute of Atomic Energy 2007

2 1 22 2 2 ν z =−εε0 +f (1+ 2 tan ν ) 2 , in which an extra 2tan ν term is included compared to the situation for a sector cyclotron. The 100 MeV high intensity compact cyclotron, CYCIAE-100, adopts straight sectors, whose shimming bar could be adjusted in an asymmetrical manner. This feature makes it feasible to improve vertical focusing by simulating the spiral configuration in certain part of the sectors. It is required that during the shimming, the shimming bar edge should not exceed the RF liner, as is shown in Fig. 2. As a consequence, a FEM model of 1/4 main magnet for CYCIAE-100 has been established accordingly. The symmetrical shimming has been conducted on the model by using successively two closed orbit codes CYCIAE and Cyclop. Fig. 3 shows the betatron oscillation frequency, whose input field data is obtained from the FEM model of 1/4 main magnet for CYCIAE-100.

Fig. 1 Sketch map of spiral sector

Fig. 2 RF liner and shimming bar edge

Apparently, the difference between vz and vz/2 turns to be small when the radius is lager than 155 cm.

According to vr∝γ, it can be deduced that vz should be adjusted to be larger to avoid Walkinshaw IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 67

oscillation, which means the vertical focusing force needs to be enhanced. As a result, the asymmetric shimming could be started at R=155 cm. In the FEM model, the edge of the shimming bar consists of a series of folding lines, the length of each line is about 2-3 cm. So we can approximate the folding lines to tangents, of which the spiral angles are formed. By choosing appropriate values of spiral angles in the model, we obtain field data; after processing these data by using Cyclop code, the corresponding betatron oscillation and phase shift data are shown in Fig. 3 and Fig. 4, respectively.

Fig. 3 Oscillation frequency comparison between isochronous shimming and asymmetric shimming

Fig. 4 Phase shift of asymmetric shimming

From the calculation above, it can be concluded that the asymmetric shimming based on spiral sector configuration could significantly improve the vertical focusing of CYCIAE-100.

Cryopumping System Design for CYCIAE-100

PAN Gao-feng, LI Zhen-guo, ZHANG Su-ping, XING Jian-sheng, ZHANG Tian-jue, CHU Cheng-jie

The cryopumping system is one of the crucial parts for the CYCIAE-100 cyclotron, through which a vacuum of 5×10－6 Pa can be achieved for the main chamber. In the mean time, it functions to qualify the 68 Annual Report of China Institute of Atomic Energy 2007 demand to accelerate H－ ions and reduce beam loss during the acceleration. However, the fact is that our past experience rarely touches upon this field, so we have to grasp the new technology in a short time. So far, it is encouraging to see that we have made significant progress in this regard in the year of 2007.

1 Heat load to the cryopumping system After the inner structure and the equipment layout have been basically determined, we proceed to conduct an insightful analysis on the characteristic and outgas of the materials in the vacuum chamber. To operate at 5×10－6 Pa, the pumping speed of cryopanels should be better than 140 000 L/s. Base on this, we put forward a solution to the cryopanel structure which agrees with the valley shape of the cyclotron. Taking into account the heat leakage of the system, the final requirement for the heat load to the cryopumping system is determined as listed below: Heat load on 4.5 K (cryopanels) : 90 W @ 4.5 K Heat load on 80 K (baffles and shields): 2 000 W @ 80 K

Fig. 1 Flow chart of 100 MeV cyclotron refrigeration system

2 Solution to cool the baffles and shields The 4.5 K cryopanels are to be cooled by liquid helium refrigerator. For 80 K baffles and shields, there are three cooling plans. 1) The liquid helium refrigerator is adopted to provide an additional route of gas helium (55 K) to the baffles and shields. 2) The qualified business machine can be used here such as Stirling refrigerator (60 K). 3) The liquid nitrogen (80 K) can be applied to the system directly. In general, there is no big difference in the running fees of the three cooling plans. Comparatively the IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 69

initial investment to solution 3 is the least, and meanwhile the liquid nitrogen can be used for the pre-cool of the liquid helium refrigerator to increase the output of liquid helium. As a result, we finally decide to adopt the third cooling plan.

3 Flow of cryopumping system After discussing with the experts and visiting TRIUMF’s facilities on the spot, we have managed to draw a reasonable flow chart of the cryopumping system for CYACIE-100 as demonstrated below (Fig. 1). It can be envisioned that the design of the cryopumping system for CYCIAE-100 will be further elaborated and improved in the near future. The following work will be emphasized on several aspects, including determination of the length and trend of liquid nitrogen and helium pipes in the light of the workshop layout, perfection to the drawing and experimental verification equipment stocking and so on.

Control System Development for CRM Cyclotron

HOU Shi-gang, YIN Zhi-guo, ZOU Jian

As a test stand for CYCIAE-100, the Central Region Model (CRM) cyclotron is an integral comprehensive machine covering all the sub-systems for cyclotron research, including water cooling, vacuum, power supply, ion source, RF generator, main magnet, control and elevating system etc. Serving as a monitoring core of the test stand, the control system plays a key role to guarantee a safe and stable running of the machine. It takes the function of parameter acquisition monitoring, remote start/stop control, interlock, and so on. Ever since the beginning of 2007, along with the progressing of beam test, all the signal wires have been laid and the test of all the devices for the control system has been accomplished. For the latter, the work involved mainly concerns the following steps. 1) Interface test Given the fact that the device interfaces are of different type and at variable logic level, we should validate the function of these equipments by controlling them via a simulation board. Then we proceed to modify the interface that fails to meet the PLC specification. After these tests, they will be connected to PLC directly for testing individually. 2) Subroutine test The second step is to debug the subroutine running in PLC for single sub-system or device. Meanwhile all the runtime condition will be set in PLC to simulate the real environment. This test will ensure the validity and integrity of subroutine of PLC. 3) Combined running After the subroutine tests, all the subroutines will be linked for a combined running. Taking use of the monitor and diagnostic function of the corresponding software provided by the PLC hardware, the program can be verified when the experiment is carrying out. 4) Further improvement to OPI The OPI (operator interface) of computer should be further ameliorated through calibrating the meter readings of field devices and OPI. In this way, the consistency of the reading between the monitor interface and the real device can be ensured, and the operators are therefore able to realize a reliable 70 Annual Report of China Institute of Atomic Energy 2007 remote manipulation and accurate adjustment to each device when needed. The vacuum system page is illustrated in Fig.1, from which the operators can startup, shutdown, supervise the parameters and status of all vacuum devices. At present most of the devices located in the vault can be controlled remotely, which ensures the safety of staff and equipment. Meanwhile, this system has enhanced the efficiency of experiment and is convenient to manipulate.

Fig. 1 Screenshot of OPI program-vacuum system page

Beam Line Design and Construction of Gas Target for a Medical Cyclotron CYCIAE-30

WEI Su-min, ZHANG Tian-jue, XING Jian-sheng, LI Zhen-guo, CHU Cheng-jie, WU Long-cheng, PAN Gao-feng, GE Tao, JIA Xian-lu, WEN Li-peng, HOU Shi-gang, WANG Zhen-hui

The first medical high intensity cyclotron CYCIAE-30 was built in China Institute of Atomic Energy (CIAE) in 1994, and it could run up to 5 000 hours each year afterward, successfully providing radioactive isotopes such as 18F, 201Tl, 68Ge to domestic hospitals periodically[1-2]. Now the upgrading project of beam lines is carried out based on the existing transport system, for which a new beam line for gas target is designed for new isotope production. After comparing different schemes of the new beam line, it is finally decided that the scheme using the existing beam line at the west extraction is chosen. The beam will deflect by 74.75° by a bending magnet when it goes through the west wall of the cyclotron vault, and then is transported towards the south until it enters the new gas target chamber. The beam will hit the solid target when the dipole does not work. This design takes the most advantage of the existing facility, the workshop is canonical and easy to realize[3]. The layout of the beam lines for solid target and the new gas target is shown in Fig.1. The layout of the beam line, the optics and the elements design such as quadrupole, dipole, steering magnet, wobbling magnet are done. The mechanical drawing and the scheme of installation of each element on the beam line are designed based on the physics design, and the design and machining of correlative parts such as vacuum system, diagnostics, control system and etc are finished. All the fabrication of these sub-systems has been accomplished in early 2007. The magnetic field IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 71

mapping and vacuum leak detection of the vacuum system are carried out in the cyclotron lab of CIAE. The result can well satisfy the requirement for the new beam line of CYCIAE-30. Fig. 2 shows the quadrupole and dipole after machining. After all the measurement work has been finished, a pre-installation of the whole line is conducted to ensure the real installation on the workshop.

Fig. 1 Layout of new beam line

Fig. 2 Quadrupole and dipole of new beam line

The installation of the new beam line and the rebuild of existing beam line of CYCIAE-30 is processing from April to May, 2007 after all the preparation is done. The beam tuning is carried out in early May, 2007. Fig. 3 shows the new beam line for the gas target. After the dipole, a quadrupole is used instead of a doublet to take the advantage of the edge-focusing-effect generated by the dipole, and thus it saves the space for the project；a doublet before gas target is located inside the wall of gas target chamber partly because of the room limit. The beam tuning is carried on the base of parameters from the physics design, Fig. 4 shows the optics simulation by code TRACE-3D[4] during the beam tuning. The result shows that the spot on the target is in accordance with the theory. After a period of tuning, all the elements and sub-systems are well-balanced, indicating that the project can be used in production. The transmission efficiency of the whole beam line is up to 96.5%.

72 Annual Report of China Institute of Atomic Energy 2007

Fig. 3 New beam line for gas target of CYCIAE-30

Fig. 4 Optics simulation of 30 MeV, 1 mA beam to solid (up) and gas (down) target on tuning

References: [1] SUN Zuxun, et al. Nuclear Science and Engineering，1997, 17(2): 157-165(in Chinese). [2] FAN Mingwu, ZHANG Tianjue. Initial Operation of CIAE Medically Used Cyclotron. Proc. of The 7th Asia Pacific Physics Conference (7APPC). Beijing, China, 1997: 19-23. [3] WEI Sumin, et al. Atomic Energy Science and Technology, 2006, 40(2): 139-144(in Chinese). [4] CRANDALL R, RUSTHOI D P. TRACE 3-D Documentation: Third Edition. Los Alamos National Laboratory, 1997.

Water-Cooling System Design of Dee for RF System of CYCIAE-100

WEI Su-min, ZHANG Tian-jue, JI Bin, XING Jian-sheng, LI Zhen-guo, JIA Xian-lu, BI Yuan-jie, AN Shi-zhong

As a compact high intensity cyclotron, CYCIAE-100, two RF cavities are installed in the two IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 73

opposite valleys to provide the accelerating voltages of 60 kV at the central region and 120 kV at the extraction region[1], the water cooling system is hard to design because of the high power feed-in. The design and optimization of Dee is shown in detail as an example. Due to the fact that the Q value can be astrict by the cavity design and manufacture, the power will loss on the cavity and bring in the cavity distortion. The RF resonance frequency will change because of this distortion. As a consequence, the water cooling is required to reduce the temperature rise and keep the temperature stability of the RF cavity so that the RF resonance frequency will remain stable. The power loss on the cavity can be calculated by a finite difference code CST MICROWAVE STUDIO. Fig.1 shows the power loss distribution on one cavity, the power loss is higher on the red region such as the edge of the Dee[2]. It can be seen that when the Q value is 10 300, about 28.1 kW RF power will be consumed on each cavity, and 48.2 kW RF power will be consumed on each cavity when the Q value is 6 000. Because of higher power loss on the edge of the Dee, the water cooling of these areas are designed and optimized first.

Fig. 1 Power loss distribution on RF cavity

Based on the power distribution of the RF cavity, the thermal analysis is carried out by a 3D finite element software ANSYS CFX[3] and the water cooling system optimization of the Dee is conducted at the same time. From the result of the numerical simulation by CST MICROWAVE STUDIO, the power loss on each Dee is 6 280 W when the Q value is 10 300 and 10 800 W when the Q value is 6 000. The thermal distribution on Dee with water cooling system is simulated according to this result. The flow velocity of water in Dee is about 3 m/s, and the liquid pressure between entrance and exit is about 1.5 kg/cm2. Given the fact that a layout with fewer water cooling tubes will induce higher temperature rise, and more water cooling tubes will result in the distortion of RF cavity by gravity, the optimization of the water cooling system is inevitable in order to reduce the number of water cooling tubes while the temperature rise is still kept acceptable. Fig. 2 shows the optimization of water cooling system of Dee. The thermal analysis demonstrates that the temperature at edge of the Dee is obviously higher than other area, and consequently the water cooling tube must go through the edge but not necessary to locate as many in the middle of the Dee. The optimization of this tube is carried out as shown in the right picture in Fig. 2. It can be seen that the tube previously in the middle of the Dee is taken out while the one on the 74 Annual Report of China Institute of Atomic Energy 2007 edge is retained. It is easier for machining and meanwhile exerts less impact on the distortion of RF cavity. There is no distinct difference in temperature rise for the two conditions because of the tube on the edge. So the final water cooling tubes on the Dee of CYCIAE-100 are located as shown in Fig. 2. Table 1 shows the power loss and temperature rise of Dee at different Q values.

Fig. 2 Water cooling tube optimization of Dee a—Initial water cooling tube; b—Optimized water cooling tube

Table 1 Power loss and temperature rise of Dee with different Q value

Q value Power loss/W Temperature rise/℃

10 300 6 280 12.6

6 000 10 800 18.3

The water cooling system design of other parts of RF system of CYCIAE-100 are proceeding, including power distribution, thermal distribution, optimization of water cooling tube, etc. These designs will be applied in the detail design.

References: [1] JI Bin, et al. Initial design of RF system for CYCIAE-100. Intramural Report, 2006. [2] JI Bin, ZHAO Zhenlu, ZHANG Tianjue, et al. The power loss on the cavity of CYCIAE100. Annual Report of China Institute of Atomic Energy. Beijing: Atomic Energy Press, 2007. [3] User document of CFX.

Design of Emittance Scanner for Intense Low-Energy H－ Beam

SONG Guo-fang, GUAN Feng-ping, WEN Li-peng

Nowadays with the fast development of nuclear physics and atomic physics, accelerator technology is widely applied in many walks of life, and along with it the requirement for beam quality produced by ion source is increasingly higher than ever. The emittance is one of the crucial parameters that define the beam quality, and consequently the research on emittance is of great value not only to the development of iron source technology, but also the accelerator-centered study as well as relevant applications. For the CYCIAE-100 cyclotron, one of the critical tasks concerns the improvement on beam quality of the iron source. As an important physical parameter for the beam, the emittance also functions as a base for the design of iron source and transfer line. The emittance scanner is designed to measure the emittance, IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 75

which is of primary importance in the beam diagnostics system.

1 Design Philosophy and Detail Structure The emittance scanner is schematically depicted in Fig. 1.

Fig. 1 Schematic of emittance scanner

We assume that the distance between deflecting plates is D, the geometric length of the plates is L, the velocity of irons is v and the angle of the irons is θ: 2D tanθ < L Based on the formula and the voltage of deflecting plates, we can determine the value of D and L. Fig. 2 shows a picture of the scanner. There is an analyzer driven by step motor. The analyzer contains two slits which are at same horizontal plane and a pair of electric deflection plates driven by a linear ramp generator. When the analyzer is mechanically driven across the beam, the front slit passes a thin ribbon of beam through the plates. The ion transit time is short compared with the ramp speed; therefore, the initial angle of the ions that pass through the rear slit is proportional to the instantaneous ramp voltage. The current through the rear slit then is proportional to the phase-space density. We can calculate the result based on the measuring data.

Fig. 2 Photograph of emittance scanner

The measuring data and the precision of it can be improved by the geometric length, the voltage of deflecting plates and the width of slit. Considering the machining difficulty of slits, it is assembled by two plates, as shown in Fig. 3. The dimension of the slit H is very thin, which can be changed later if necessary. And one restrained plate is used to reduce the measuring error. 76 Annual Report of China Institute of Atomic Energy 2007

Fig. 3 Structure of slits

2 Conclusion This emittance scanner is most useful for the measurement of H－ beams at low energy. However, for the high energy beams, it can be only applicable provided that an excessive scan voltage is provided for the deflecting plate and big modification on the dimension and inner structure of the analyzer is made. The length of the scanner is determined primarily by the required angular resolution and the precision with which the small slit width H can be maintained. This slit must be thin enough to let irons pass with angles θ without collection. Because of its special structure, the emittance scanner is of high-accuracy in measurement while featuring a compact and simple design.

Progress Report of Beijing Radioactive Ion-Beam Facilities (BRIF) in 2007

CAO Xiao-ping, SUN Yang

Beijing Radioactive Ion-beam Facilities (BRIF) project is in progress in 2007. In the working drawing design of the project has made a great step forward, and some critical equipment ordering were finished. The project is in the preparing stage for the construction start working.

1 Cyclotron The compact 100 MeV, 200 µA proton cyclotron is the driver machine of BRIF. The cyclotron main magnet, the RF powers and RF transmission line were finished ordering. The test bench for central region of the cyclotron was under construction and commissioning. Also, the tests of the bench for central region and the high frequency power calorimetry for resonator are made good help for the mechanical design.

2 Isotope separator on line (ISOL) The mechanical design of target ion source is underway, the optimization of the extraction electrode has been carried out to minimize the beam emittance. The mechanical parameters of seven dipole magnets have been determined. And the hot cell for the target ion source maintenance is under ordering. The designs of other system such as vacuum system, control system, cooling system, HV platform and ion source test bench etc. are in progress, they are expected to be finished in next year.

3 Superconducting booster The 2 MeV/q superconducting booster was in the stage of construction. The cupper Quarter-Wave IMPORTANT NUCLEAR SCIENCE ENGINEERING·Beijing Radioactive Ion-Beam Facility 77

Resonators (QWR) was under machining. The cryostat has been assembled for the vacuum test and liquid nitrogen cooling test. The key components of Ni-sputtering chamber have finished. The QWR is ready for Nb-sputtering technology research in 2008.

4 Injector The test running of HI-13 tandem injector upgrading has been finished by the end of 2007. The injector platform high voltage 300 kV runs stably, and the design aims of the mass resolution and the transmission efficiency have been reached.

Progress of Superconducting Booster of BRIF Project in 2007

ZHOU Li-peng, PENG Zhao-hua, LV Zhao, ZHENG Jian

The superconducting booster is a main part of the Beijing Radioactivity Ion-beam Facility project (BRIF). As the designed target of the superconducting booster, a energy gain 2 MeV/q for β=0.118 ions will be expected. The booster consists of ten subsystems: 4 superconducting cavities, a cryostat, a set of vacuum system, a cryogenic system, beam transport line, beam pulsing system, radio frequency system, control system, cleaning room and Niobium sputtering technology. The quarter wavelength resonators will be adopted in the superconducting booster. The operating frequency is 150.4 MHz, and acceleration field is 3.5 MV/m. A sample copper cavity is being made at present. We are developing the machine tuner with the frequency adjustment precision of 1 Hz corresponding to 0.37 μm of the machine precision. Liquid nitrogen will be used as thermal cold shield and liquid helium is used for resonators cooling. The cavities share the same cryostat isolation vacuum. We have a turbo molecular pump with 2 000 L/s, a dry pump with 8 L/s and two ion pumps with 1 000 L/s using for the cryostat vacuum. The cryostat has been assembled, and the company is preparing the vacuum test. Low energy beam pulsing system is used for matching time-acceptance of superconducting booster and increasing the beam utilization efficiency of rare isotope beams. A double drift buncher is designed with variable frequencies around 6 MHz and 12 MHz. A traveling wave chopper will be installed before the buncher. At present, some special components are developed. The radio frequency system provides RF power, base phase and base time for the superconducting booster and low energy bunching system. The operating frequency of the booster is 150.4 MHz and the fundamental frequency of the bunching system is 6 MHz. The independence phase control is adopted in the each RF loop. We have begun to develop with other company, and now we are debugging the printed circuit boards of the TWC driver, the resonator controller and the low noise per-amplifier. The technical specifications about Nb sputtering equipments are ready. The sputtering chamber is being made by a company. In the first half of 2008, the clean room, the sputtering chamber, vacuum pumps and so on will be assembled, and then the next work is to do research for Nb sputtering technology. We had got a good progress in design and development of the key components of the superconducting booster in 2007. In the next year, to develop the control software, to develop the low energy beam pulsing system and to build the sputtering platform will be keystone for us. In a word, the superconducting booster is going as our schedule.

78 Annual Report of China Institute of Atomic Energy 2007

Current Status of Isotope Separator On-Line of BRIF Project (BRIF-ISOL)

CUI Bao-qun, MA Ying-jun, MA Rui-gang, TANG Bing, HUANG Qing-hua, JIANG Cong, JIANG Wei-sheng

The design of BRIF-ISOL has been in progress in 2007, the major progresses related to the project are reported. The mechanical design of target ion source is underway, the optimize of the extraction electrode has been carried out to minimize the beam emittance. The handling scheme of radioactive ion source and its nearby instruments is further optimized, within this scheme, the target ion source and its nearby instruments are assembled into different modules, the module can be removed to a hot cell for maintenance without manual intervene. A demonstration prototype has been designed and will be tested soon. The LD31 Aluminum alloy has been selected as the material of the vacuum chamber for target ion source and nearby instruments to reduce the activation caused by high energy neutrons from target. The suppliers of the hot cell for maintenance of target ion source have been contacted for manufacture; the contract will be signed soon. The mechanical parameters of seven dipole magnets in BRIF-ISOL have been determined; they are ready for placing order. To eliminate the aberration from the magnets, 3rd order surface coils have been tested on an existing dipole, the measurement value is well consistent with design value. The problems found in the test such as higher temperature of circuit board, non-zero field in the center will be further investigated. The parameters of apparatus for magnetic field measurement have been determined and the suppliers has been contacted, it is ready to place order. The field distribution of the electrostatic lens used in BRIF-ISOL has been calculated and its mechanical design will be carried out. In the aspect of beam diagnostics instruments, the assembly drawing of emittance and wires scanner has been finished. The physical design of a emittance instrument for 300 keV beam has been finished. A prototype CsI BPM which visualizes the beam profile has been tested with 30 keV ion beam, the image of beam with intensity down to 108 s－1·mm－2 can be observed. Further investigation for lower beam intensity will be carried out soon. Also the investigation to measure low beam intensity down to 106 s－1 with faraday cup is under way. A energy spread instrument has been tested. The design of primary beam diagnostics and beam distinguish instruments is underway. The design of BRIF-ISOL vacuum has been assessed by a group of vacuum experts. The design is accepted by experts. The concept design of exhausted gas from vacuum chamber has been finished. Some works on radiation hard sealing materials and low activation material used in target area has been carried out. Also the efforts to modify some material in turbo pump used in target area are underway. The design of computer control system for BRIF-ISOL is nearly finished. The design drawing of electrical has been finished. The parameters of HV power supplies and HV related parts such as 300 kV with high stability and low ripple, 50 kV HV power supply with low ripple and acceleration tube are determined and their possible suppliers are contacted, it is ready to place the orders. A type of HV conduit which is made of glass epoxy has been suffered the irradiation test up to 109 rad, the electrical result shows this type conduit is capable of being used in lower radiation environment. Another type of HV conduit which is made of porcelains insulator and compressed SF6 is under investigation, this type HV conduit is expected to work in very high radiation environment, a prototype conduit has been manufactured and will be tested soon. The designs of other auxiliary system such cooling system, HV platform and ion source test bench etc. are in progress, they are expected to be finished in next year.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 81

Nuclear Physics

Tetrahedral Symmetry in Superheavy Nuclei*

CHEN Yong-shou, GAO Zao-chun

The issue that underlies the present investigation is whether some heaviest atomic nuclei can be characterized as having the intrinsic mean fields with the tetrahedral symmetry which is quite common in molecular, metallic clusters and other many quantum objects. The tetrahedral symmetry is a direct consequence of the theory of the point group and corresponds to the invariance under the transformations D of the group Td which has two one- and one four-dimensional irreducible representation. In molecular and metallic clusters, the tetrahedral symmetry is determined by the mutual geometric arrangement of the constituent ions. In atomic nuclei, as a strong interaction and finite many body systems, the situation is more complicated and the nuclear shape is governed by the shell effects. The tetrahedral symmetry in nuclei has been a subject of great interest, e.g., sees Ref. [1]. The theoretical prediction for the tetrahedral deformation in nuclei is rather convincing, however, it has not been confirmed experimentally. The tetrahedral symmetry in nuclei is realized at first order through the nonaxial octupole deformations of the nuclear density corresponding to the intrinsic moment Q32, associated with the Y32 deformed shape. Moreover, the octupole correlations and quadrupole mode are often in competition, so that the manifestation of the tetrahedral symmetry is somewhat obscurant. The present study will concentrate on the possibility that the tetrahedral symmetry may realize as the exotic Y32 shape in some superheavy nuclei, where the possible experimental evidences have already been implied in the new spectroscopy data. The purpose of the present article is to investigate for the first time the role of the nonaxial octupole configurations in the collective excitations of superheavy nuclei. There has been experimental observation of low-energy 2－ bands in the mass-250 region. For example, for the N=150 isotonic chain, early data showed a 2－ band in 246Cm with an bandhead energy E(2－) = 0.842 MeV , and in 248Cf with a much lower band head E(2－)= 0.592 MeV[2-5]. The recent data have added new evidences for 250Fm with E(2－)=0.879 MeV and for 252No with E(2－)= 0.929 MeV[2-5]. It is unlikely that these bands are negative-parity 2-quasiparticle (qp) excitations since a 2-qp state must have an energy greater than two times of the BCS pairing gap, therefore, any 2-qp state should lie higher than 1 MeV above the ground state. We prefer to interpret these 2－ bands to be of collective nature, manifesting the nonaxial octupole deformation, the Y32 shape, which is superposed with the quadrupole deformation. We have generalized the Reflection Asymmetric Shell Model (RASM)[6] to include the triaxiality and realize a full quantum treatment of quadrupole and nonaxial octupole degree of freedom of nuclear surface and then explore the dynamical effects beyond the mean-field, the parity and angular momentum restorations, to study whether the collective states with reasonable nonaxial octupole correlations can appear at the low-lying excitation energy, and whether the experimental 2－ bands at few hundreds of keV, observed in the A=250 region, can be reproduced systematically by the present calculation and interpreted 82 Annual Report of China Institute of Atomic Energy 2007

as the possible evidence for nonaxial octupole Y32 modes in these heaviest nuclei. By using the triaxial RASM we calculate the low-lying spectrum in these nuclei. The standard Nilsson potential parameters are used and three major shells for each kind of nucleon (major shells 5, 6, 7 for neutrons and 4, 5, 6 for protons) are considered. The monopole pairing strength G0 takes the usual form G0=g1+g2(N－Z)/A, with g1=20.36 MeV and g2=11.26 MeV, and the quadrupole pairing strength is set to G2=0.13G0. In the present work, we fix the quadrupole deformation ε2=0.235 for all nuclei; this value is verified to be consistent with that obtained from the TRS calculations. The octupole deformation － parameter ε32 influences sensitively the excitation energy of the 2 band relative to the ground state. We 246 found that to reproduce data, the best suitable values are: ε32=0.105, 0.118，0.110 and 0.107 for Cm, 248Cf, 250Fm and 252No, respectively. The calculated results are compared with experimental data in Fig. 1. The agreement between experiment and theory is excellent. The reduced E3 transition probability B(E3; 0+→3－) is calculated for the Coulomb excitation from the 0+ ground state to the 3－ state of the 2－ band for each nucleus. The future experiments on the measurements of the E3 transitions will be crucial for the final conclusion of the collectivity of these 2－ bands, as well as its tetrahedral symmetry.

Fig. 1 RASM calculations for ground band and 2－ band in N=150 isotones The theoretical results are compared with available data

The calculated B(E3; 0+→3－) value in Weisskopf units for each nucleus is marked by ‘×’

References: [1] DUDEK J, CURIEN D, DUBRAY N, et al. Phys Rev Lett, 2006, 97: 072501. [2] ARTNA-COHEN A. Nucl Data Sheets, 1998, 84: 901. [3] AKOYALI Y A. Nucl Data Sheets, 1999, 87: 249. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 83

[4] PRITCHARD A. Ph. D. Thesis, Liverpool, 2006. [5] SULIGNANO B, et al. Eur Phys J A, in press. [6] CHEN Y S, GAO Z C. Phys Rev, 2000, C63: 014314.

* Supported by National Natural Science Foundation of China (10475115, 10305019, 10435010), Chinese Major State Basic Research Development Program (2007CB815000)

Microscopic Optical Potentials of Nucleon-Nucleus and Nucleus-Nucleus Scattering*

MA Zhong-yu, MA Yin-qun, RONG Jian

The relativistic microscopic optical potential (RMOP) in the nucleon-nucleus scattering is studied in the framework of the Dirac Brueckner Hartree-Fock (DBHF) approach. The real part of the nucleon self-energy in asymmetric nuclear matter is calculated with the G-matrix, while the imaginary part is obtained from the polarization diagram. Nuclear optical potentials in finite nuclei are derived from the nucleon self-energies in asymmetric nuclear matter through a local density approximation. The RMOP is applied to study the nucleon scattering off stable nuclei and nucleon effective mass. A satisfactory agreement with the experimental data is found. The complex nucleon-nucleus optical potential is extended to microscopic optical potentials of nucleus-nucleus interaction by a folding method. The elastic scattering data of 6He at 229.8 MeV on 12C target are analyzed.

* Supported by National Natural Science Foundation of China (10475116, 10535010), Major State Basic Research Development Program in China (2007CB815000), European Community Project Asia-Europe Link in Nuclear Physics and Astrophysics (CN/ASIA-LINK/008(94791))

Inner Crust of Neutron Stars in Relativistic Mean Field Approach*

CAO Ji-guang1, MA Zhong-yu, Nguyen Van Giai1 (1 Institute of Nuclear Physics, Paris University, France)

The microscopic properties and superfluidity of the inner crust in neutron stars are investigated in the framework of the relativistic mean field (RMF) model. The Wigner-Seitz (W-S) cell of inner crust is composed of neutron-rich nuclei immersed in a sea of dilute, homogeneous neutron gas. In this work, we emphasize on the choice of the boundary conditions in the RMF approach. Three kinds of boundary conditions are suggested. The properties of the W-S cells with the three kinds of boundary conditions are investigated. The RMF model with parameter set of DDME1 with density dependent coupling constants is adopted in the calculations. The densities of the W-S cells in our calculations are chosen as those suggested by Negele and Vautherin (Table 1)[1]. In order to describe the unbound and homogeneous neutron gas in the W-S cells, we have to choose proper boundary conditions for the single-particle wave functions. The first kind of boundary conditions we used is similar with what has been used in the non-relativistic approach, i.e., the upper component of 84 Annual Report of China Institute of Atomic Energy 2007

even parity wave functions vanish at the cell radius Rc while the first derivative of the upper component of odd-parity wav functions vanishes at r=Rc. This is denoted as boundary condition C. Unfortunately, it is seen that with the above boundary condition C the orthogonality of the single-particle wave functions is not fulfilled. However, we have checked that the violation of the orthogonality in case C is not large, generally less than 10－3. Therefore, in our calculations we also adopt the boundary condition C for comparison. In order to satisfy the orthogonality two kinds of boundary conditions in this work are suggested, boundary condition A: the upper component of even parity wave functions vanish at the cell radius Rc while the lower component of odd-parity wav functions vanishes at r=Rc and boundary condition B: the upper component of wave functions with positive κ vanish at the cell radius Rc while the lower component of wave functions with negativeκvanishes at r=Rc. It is clear that the single-particle wave functions with the boundary conditions A and B are orthogonal to one another. Nine regions of the inner crust with densities had been determined by Negele and Vautherin. The calculated binding energies per nucleon and average neutron gas densities in the RMF with DDME1 are given in Table 1. The results with the three kinds of boundary conditions are compared. The differences of

(E/A) in the three cases are less than 2.5%, whereas the average neutron gas densities ρg are very similar.

ρg increases significantly with increasing inner crust density.

Table 1 Comparison of binding energy per nucleon (E/A) and average neutron gas density (ρg) obtained with boundary conditions A, B and C

－3 (E/A)/MeV ρg/fm W-S cell(Z,N) A B C A B C

(40, 140) －5.153 －5.143 －5.153 8.56×10－5 8.56×10－5 8.55×10－5

(40, 160) －4.617 －4.569 －4.589 1.51×10－4 1.51×10－4 1.51×10－4 (40, 210) －3.567 －3.513 －3.543 2.94×10－4 2.94×10－4 2.94×10－4 (40, 280) －2.545 －2.512 －2.564 5.29×10－4 5.29×10－4 5.29×10－4 (40, 460) －1.089 －1.073 －1.139 1.15×10－3 1.15×10－3 1.18×10－3 (50, 900) 0.300 0.265 0.145 3.04×10－3 3.05×10－3 3.05×10－3 (50, 1 050) 0.949 0.866 0.733 4.76×10－3 4.77×10－3 4.84×10－3 (50, 1 300) 1.707 1.619 1.450 7.50×10－3 7.53×10－3 7.55×10－3 (50, 1 750) 3.453 3.214 2.959 1.74×10－2 1.74×10－2 1.74×10－2

In summery, the properties of the inner crust of neutron stars are studied in the relativistic mean field framework for the first time. In order to describe the unbound and homogeneous neutron gas in the W-S cells three kinds of boundary conditions are proposed in our calculations. It is found that the boundary condition C among the three boundary conditions produces the flattest neutron gas density distribution and the lowest binding energy per nucleon. The boundary conditions A and B with full orthogonality give more or less similar neutron gas density distributions. With a proper boundary condition the RMF approach could reasonably describe the structure of the W-S cell.

Reference: [1] NEGELE J W, VAUTHERIN C. Nucl Phys, 1973, A207: 298.

* Supported by National Natural Science Foundation of China (10475116, 10535010), Major State Basic Research Development Program in China (2007CB815000), European Community Project Asia-Europe Link in Nuclear Physics and Astrophysics, CN/ASIA-LINK/008(94791)

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 85

Relativistic Quasiparticle Random Phase Approximation With a Separable Pairing Force*

TIAN Yuan, MA Zhong-yu, Peter Ring1 (1 Physik Department, Technische Universität München)

A new pairing force has been derived from Gogny effective interaction in nuclear matter. And in the ground states of the spherical nuclei, this pairing force has a simple separable form. It can be easily applied in the calculation of finite nuclei, and gives almost the same pairing properties as the Gogny force. In this paper, we will investigate this new pairing force in the vibration excited states in the Relativistic Quasiparticle Random Phase Approximation (RQRPA). As seen from the figure, we

calculate E2 (Fig. 1a) and B(E2) (Fig. 2) values of Sn isotopes. The dots represent the experiment data, the diamond points are the results with Gogny pairing interaction, and the star points correspond to the results of our new separable force. Therefore, this simple separable pairing force can well depict the pairing properties not only in the ground states of spherical nuclei, but also the vibration excited states. And it will be applied in the calculation of deformed nuclei in the future.

Fig. 1 E2 (a) and B(E2) (b) values for Sn isotopes as a function of neutron number

a: ●—Exp. value, ■—NL3+D1S, *—NL3+Sep; b: ●—Exp. value, ■—Gogny D1S, *—Separable

* Supported by National Natural Science Foundation of China (10475116, 10535010), Major State Basic Research Development Program in China (2007CB815000), European Community Project Asia-Europe Link in Nuclear Physics and Astrophysics, CN/ASIA-LINK/008(94791)

Effect of Tensor Interaction on Spin-Orbit Splitting*

ZOU Wei1, 2, Gianluca Colò2, MA Zhong-yu, Hiroyuki Sagawa3, Pier Francesco Bortignon2 (1 Physics Department, Jilin University, China; 2 Dipartimento di Fisica, Universit`a degli Studi and INFN, Sezione di Milano, via Celoria 16, 20133 Milano, Italy; 3 Center for Mathematical Sciences, University of Aizu, Aizu-Wakamatsu, Fukushima 965-8560, Japan)

The Skyrme parameter sets were widely used in nuclear structure calculations which did not include 86 Annual Report of China Institute of Atomic Energy 2007

the sensor contribution. Until recently, some attentions have been paid to study the effects of the tensor force on the evolution of the shell structure of atomic nuclei. In an attempt to reach a global view of the effects of the tensor interaction on single-particle states in nuclei, we analyze the role of the zero-range tensor associated with a Skyrme-type effective force on the spin-orbit splitting in Ca isotopes and in the N=28 isotones. The role of the surface and volume pairing forces are discussed. The different role of the triplet-even and triplet-odd tensor forces is pointed out by analyzing the spin-orbit splitting in these nuclei. In the present work, which is a follow-up of Ref. [1], we consider the tensor interaction: - - - - 2 2 vT= / 2{[(σσ⋅⋅kk ' )(212212 ' ) 1/3 k ' ( σσ ⋅ )]δ ( rrkk )+'' [( σσ ⋅⋅ )( ) 1/3( σσ ⋅ ) krr ]δ ( )}+ T 112112- - - U'{(σσσσ112⋅⋅⋅⋅krr )δ (122 )( k'' ) 1/3( )[ kδ ( rrk 12 ) ]} and extend our study of the tensor correlations to lighter systems(Ca isotopes and N=28 isotones). We have performed a study of the Ca isotopes. By comparing the pairing gap near the Fermi surface (i.e.,

Δ(f7/2)) and average pairing gap with the result of the three-point and five-point formulas respectively, we 3 can fit a suitable parameter V0=740 MeV·fm in the case of the density-dependent δ interaction (DDDI). If 3 we wish to use the simple δ force (DF), we must use V0=305 MeV·fm . Then we calculate the single-particle energy level under the framework of HF-BCS. Fig. 1 shows the energy differences between the sd proton states as a function of the mass number A. We compare the results consider and without consider the tensor force with the experimental data. One can notice a substantial improvement due to the inclusion of the tensor interaction. In particular, the experimental results in the magic isotopes 40Ca and 48Ca are perfectly reproduced. In order to get more understanding on the effects of the tensor force on single-particle states in nuclei, we also consider the evolution of the spin-orbit splitting along the N=28 isotones and we can get a similar result. From what we have discussed above, we can get a conclusion that the effect of tensor force can improve the results of spin-orbit splitting not only for heavy nuclei but also for the medium-mass nuclei.

Fig. 1 Energy differences between 1d3/2 single-proton state (kept fixed) and, respectively,

2s1/2 and 1d5/2 states, plotted along the Ca isotopes ◀—Without considering tensor effect；●—Considering tensor effect；

☆—Experimental result

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 87

Fig. 2 Energy differences between 1d3/2 single-proton state (kept fixed) and, respectively,

2s1/2 and 1d5/2 states, plotted for the N=28 isotones △—Without considering tensor effect；○—Considering tensor effect；☆—Experimental result

Reference： [1] COLÒG, SAGAWA H, FRACASSO S, et al. Phys Lett, 2007, B646: 227.

* Supported by National Natural Science Foundation of China (10475116, 10535010), Major State Basic Research Development Program in China

(2007CB815000), and European Community Project Asia-Europe Link in Nuclear Physics and Astrophysics, CN/ASIA-LINK/008(94791)

Probing Density Dependence of Symmetry Energy With Heavy Ion Collisions

ZHANG Ying-xun1, 2, 3, P. Danielewicz2, 3, 4, M.B. Tsang2, 3, 4, W. G. Lynch2, 3, 4, LI Zhu-xia1 (1 Department of Nuclear Physics, China Institute of Atomic Energy, Beijing 102413, China; 2 Joint Institute of Nuclear Astrophysics, Michigan State University; 3 National Superconducting Cyclotron Laboratory, Michigan State University; 4 Physics and Astronomy Department, Michigan State University)

Information about the Equation of State (EOS) of asymmetric matter improves our understanding of the properties of neutron star such as stellar radii and moments of inertia, maximum masses, crustal vibration frequencies, and neutron star cooling rates, which are currently being investigated with ground-based and satellite observations. But it is still uncertain. The extrapolation of the EOS to neutron–rich matter depends on the density dependence of the nuclear symmetry energy, which has comparatively few experimental constraints. The influences of symmetry energy and in medium NN cross section on the isospin sensitive observables are explored with QMD model (Fig. 1). Our results show that the symmetry potential plays important role on the double neutron to proton ratio and the isospin transport ratio Ri rather than on the in medium NN cross section. In addition, different isospin tracers are adopted to construct the isospin transport ratio. And our study shows, isospin transport ratio constructed from different isospin tracer give different values.

88 Annual Report of China Institute of Atomic Energy 2007

Fig. 1 Isospin transport ratio Ri obtained with different tracer

■—X=δ, (n+Frag.); ●—X=ln (n/p); △—X=δ, v cut; ◇—X=δ, Zmax>20

Exploring Symmetry Energy With Emitted Neutrons and Protons Using Quantum Molecular Dynamics Model*

ZHANG Ying-xun1, 2, 3, P. Danielewicz2, 3, 4, M. Famiano5, LI Zhu-xia1, W. G. Lynch2, 3, 4, M.B. Tsang2, 3, 4 (1 Department of Nuclear Physics, China Institute of Atomic Energy, Beijing 102413, China; 2 Joint Institute of Nuclear Astrophysics, Michigan State University; 3 National Superconducting Cyclotron Laboratory, Michigan State University; 4 Physics and Astronomy Department, Michigan State University; 5 Physics Department, Western Michigan University)

Information about the Equation of State (EOS) of asymmetric matter improves our understanding of the properties of neutron star such as stellar radii and moments of inertia, maximum masses, crustal vibration frequencies, and neutron star cooling rates, which are currently being investigated with ground-based and satellite observations. Recent observations of neutron stars with the XMM-Newton X-ray telescope have been interpreted as requiring an unusually repulsive equation of state for neutron matter. It is important to determine whether such interpretations are supported by laboratory measurements. Measurements of isoscalar collective vibrations, collective flow and kaon production in energetic nucleus-nucleus collisions have constrained the equation of state for symmetric matter for densities ranging from normal saturation density to five times saturation density. On the other hand, the extrapolation of the EOS to neutron-rich matter depends on the density dependence of the nuclear symmetry energy, which has comparatively few experimental constraints. Two kinds of density dependence of symmetry energy are plotted in Fig. 1. In this work, emissions of free neutrons and protons from the central collisions of 124Sn+124Sn and 112Sn+112Sn reactions are simulated using the Improved Quantum Molecular Dynamics model with two different density dependence of the symmetry energy in the nuclear equation of state. The constructed double ratios of the neutron to proton ratios of the two reaction systems are found to be sensitive to the symmetry terms in the EOS. The effect of cluster formation is examined and found to affect the double ratios mainly in the low energy region. In order to extract better information on symmetry energy with transport models, it is therefore important to have accurate data in the high energy region which also is affected minimally by sequential decays. In summary, the double neutron to proton ratio that is predicted from the QMD model favor the soft FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 89

symmetry energy case, where the parameters of symmetry energy γ=0.5 (Fig. 2).

Fig. 1 Density dependence of symmetry energy, γ=0.5, 1.0, 2.0

Fig. 2 Double neutron to proton ratio, compare with MSU data a—ImQMD, b=2 fm; b—Coalescence invariant

★—Data; ◇—IBUU04

* Supported by National Natural Science Foundation of China (10675172)

Analysis of Intermediate Energy Proton-Induced Spallation Reactions by Improved Quantum Molecular Dynamics Plus Statistical Decay Model

OU Li, ZHANG Ying-xun, LI Zhu-xia

The spallation reactions have wide applications in material science, biology, surgical therapy, space engineering and cosmography. Thus there is the growing need of nuclear data for spallation reactions at intermediat energies up to 1 GeV for various targets, not only for the neutron production nuclei such as Pb, 90 Annual Report of China Institute of Atomic Energy 2007

Bi, W, but also for surrounding structural materials such as Al, Fe, Ni, Zr and biologic elements such as C, O, Ca. Experiment data on neutron or proton double differential cross sections are important for all of above applications. However, it is impossible to make measurements for all data that are of importance for the various applications, especially for the unstable nuclei. In this work, the improved Quantum Molecular Dynamics model (ImQMD05) and the statistical decay model is adopted to study the intermediate energy proton-induced spallation reactions with various target. The influences of the different Skyrme interactions on the mechanism of spallation reaction and the double differential cross sections of emitted neutrons are studied. It is found that the different Skyrme interactions influence the low energy part of spectrum of emitted nucleons. This effect decreases as incident energy become higher. The double differential cross sections of emitted neutrons are found to be in good agreement with experimental data when the Skyrme parameter set SkP is adopted.

Modified Woods-Saxon Potential for Heavy-Ion Fusion Reaction

TIAN Jun-long, LI Zhu-xia, WANG Ning, ZHANG Ying-xun

Research on nucleus-nucleus interactions potential in heavy-ion fusion reactions has attracted a great deal of attentions for understanding the nuclear reaction near barriers. The macroscopic potentials such as Woods-Saxon potential, proximity potential and Bass potential are widely used, but most of these macroscopic approaches lost some microscopic properties of nuclei, such as shell effects. On the other hand, the nucleus-nucleus potential can also be calculated with the microscopic nucleon-nucleon interaction or realistic density distribution of nuclei in order to avoid the deficiency of macroscopic approach. From the theoretical view point, these models provide more accurate information for heavy-ion reactions at energies near barrier, but it is more complicated on computing than that with macroscopic approach. In our work, a modified Woods-Saxon (MWS) potential is proposed for describing nucleus-nucleus interaction based on the Skyrme energy-density functional approach. Fusion barriers for a larger number of fusion reactions from light to heavy systems can be described well with this potential. The suitable incident energies for fusion reactions leading to super-heavy nuclei are also explored. It seems that the MWS potential is useful for selecting the suitable incident energies for fusion reactions for producing super-heavy nuclei.

Specific Heat in Hadron and Quark-Gluon Matters

SA Ben-hao, LI Xiao-mei, HU Shou-yang, -ping, FEN Jing

A parton and hadron cascade model, PACIAE, is applied to follow the particle transport in partonic and the hadronic stages in 0%-5% most central Au+Au collisions at energies from SPS to RHIC. We have determined the specific heat of hadron matter (π++π－) in the hadronic final state and the specific heat of quark-gluon matter (u+d+g) in the partonic initial state in Au+Au collisions as a function of the reaction energy (excitation function). It turns out that the QGM specific heat is hard to survive the hadronization FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 91

and there is not a peak structure in the specific heat excitation functions in studied energy region[1].

Reference: [1] SA Benhao, et al. Phys Rev, 2007, C75: 054912.

Direct Photon Production in p+p and Au+Au Collisions

at SNN =200 GeV in PACIAE Model

LI Xiao-mei, LI Shou-ping, HU Shou-yang, ZHOU Feng, SA Ben-hao

A parton and hadron cascade model, PACIAE, is used investigating the PHENIX data of the direct 0 0 photon and π invariant differential cross section in p+p collisions and the direct photon and π pT distributions in 0%-10% most central Au+Au collisions at top RHIC energy. It turns out that the data above are possible to be described by this microscopic transport model[1].

Reference: [1] LI Xiaomei, et al. J Phys G: Nucl Part Phys, 2007, 34: S837.

Rotational Structures at Ultrahigh Spin in 157, 158, 159Er

DONG Bao-guo, MA Hai-liang, YAN Yu-liang

Rotational structures at high spin and ultrahigh spin, including properties of shape coexistence and termination, in 157,158,159Er, were investigated with the configuration-dependent cranked Nilsson- Strutinsky approach. The theoretical calculations demonstrate that for terminating bands the total angular 146 158 momenta of 12 aligned valence nucleons outside the 64Gd82 doubly magic core in Er, i.e. angular momentum of terminating state, are 46+, 48－, and 49－, and this is in very good agreement with experimentally observed results, so the calculated results are considerably reliable. The corresponding 4 6 2 4 5 3 assigned configurations are π(h11/2) 16⊗ν(h9/2f7/2) 18(i13/2) 12 and π(h11/2) 16⊗ν(h9/2f7/2) 15.5, 16.5(i13/2) 16.5. For the recently observed rotational band 1 in 158Er, the highest spin of discrete states is extended up to 146 65= and beyond the terminating spin mentioned above, the 64Gd82 core has to be broken to generate further angular momentum. Based on the theoretical calculations, the possible configuration for band － 4 6 1 1 1 is proton configuration π[(g7/2d5/2) 10(h11/2) 18(h9/2f7/2) 4.5(i13/2) 6.5]39 and neutron configurationν －2 －2 8 4 [(Nosc=4)2 (h11/2)10 (h9/2f7/2) 19, 20(i13/2) 20]51, 52, of which the maximum spin is up to 90= and 91=. There is shape coexistence within the same configuration from low spin to high spin states. The calculated deformations, e.g. (ε2, γ, I)=(0.36, 22°, 31), (0.34, 22°, 51) and (0.34, －15°, 51), indicate that observed band 1 in 158Er is highly deformed. Other possible configurations for band 1 of 158Er are discussed. 157 158 Ultrahigh-spin band of Er is similar to that of Er, configuration of observed band 1 is one i13/2 neutron less than the corresponding configuration of 158Er. For 159Er, the calculations demonstrate that 158 there are possible configurations and ultrahigh-spin bands similar to that of Er, i.e. adding a h9/2f7/2 neutron in the neutron configuration of 158Er is the corresponding configuration of 159Er, and the 92 Annual Report of China Institute of Atomic Energy 2007

maximum spin could be built up to 90.5 = and 91.5 = . The calculated deformations, e.g. (ε2, γ, I)= (0.36, 21°, 30.5), (0.35, 22°, 50.5) and (0.34, －16°, 50.5), indicate that predicted corresponding bands in 159Er is highly deformed. For experimental observations, ultrahigh-spin bands in 159Er are more difficult than that in 158Er because of 159Er about 0.5 MeV higher in energy.

Theoretical Models of Cell Inactivation by Ionizing Particles*

CAO Tian-guang, MA Yun-zhi1, KONG Fu-quan, YANG Ming-jian2, ZHUO Yi-zhong (1 Key Lab of Medical Physics and Engineering, , Beijing 100871, China; 2 School of Sciences, University of Technology, Tianjing 300130, China)

Ionizing radiation can induce various kinds of biological effects, its relative biological effectiveness (RBE) changes not only with the type of radiation and its energy, but also with the type of biological target and the biological end point concerned. The cell survival curve describes the relationship between the fractional survival of a population of radiated cells and the dose of radiation to which the cells are exposed. The end point for survival in experiments is referred to the ability of a cell to reproduce (reproductive death). It does not describe the continued existence of a single cell. The theoretical models estimating the fraction of surviving cells are of the utmost importance to the application of ionizing radiation in radiotherapy. The track structure model can simulate the transport of charged particle in medium and give the spatial distribution of the energy deposit in the scale of nanometer. Considering the stochastic of the energy deposit, a concept of ionization clustering cluster to model the mechanism of lethal damages production is proposed, which is called ICC model. For deuteron ions at two cell cycle phases the survival curves are calculated and show in Fig. 1. The results are in good agreement with the experimental data.

Fig. 1 Calculated survival curves compared with those measured by exposing Chinese hamster V79 cells to mono-LET charged particles

●—Bird et al., 20 keV/μm deuteron; ▲—Bird et al., 40 keV/μm deuteron,

Solid line—ICC model, 20 keV/μm deuteron; Open line—ICC model, 40 keV/μm deuteron

In order to understand some of the mechanisms of DNA damage related to cell killing and their dependence on radiation quality, the yields of single track lethal events are compared with the estimated yields of different classes of complex DNA lesions calculated using fast Monte-Carlo method. The results FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 93

show that the majority of DNA damage is repaired in a way that is non-lethal[1].

Reference: [1] CAO Tianguang, MA Yunzhi, KONG Fuquan, et al. Nuclear Physics Review, 2007, 24(2): 94-97.

* Supported by National Natural Science Foundation of China (10647146, 10435020, 10175095)

Monte-Carlo Simulation of Cellular S Value and Specific Energy for Electrons*

GENG Jin-peng1, MA Yun-zhi2, CAO Tian-guang, LI Yu-xiao1, ZHUO Yi-zhong (1 School of Physical Science and Technology, Zhengzhou University; 2 Key Lab of Medical Physics and Engineering, Peking University)

Various ionizing radiations transfer their energy to biological media by produced secondary electrons. In the diagnosis and therapy of nuclear medicine and BNCT, the radionuclides distribute heterogeneously at cellular scale. In order to understand the interaction between ionizing radiation and biological medium, the study of cellular microdosimetry for electrons is needed. S value and the single event specific energy distribution are simulated by several codes, which include different Monte-Carlo method[1]. The result for S value is agreement basically with the result of the MIRD committee and other simulations. The single-event specific energy distribution in cell is agreed well with the result of the Penelope code (Fig. 1).

Fig. 1 Single-event specific energy distribution f1(z) of 100 keV electron from cell surface to cell nucleus ▲—MOCA15；●—Penelope；○—TRAX；△—Geant4

Reference: [1] GENG Jinpeng, MA Yunzhi, CAO Tianguang, et al. Atomic Energy Science and Technology, 2007, 41(1): 14-19.

* Supported by National Natural Science Foundation of China (10435020, 10175095)

94 Annual Report of China Institute of Atomic Energy 2007

Study on High-Spin State and Signature Inversion in 110Ag*

HAO Xin, ZHU Li-hua, WU Xiao-guang, LI Guang-sheng, HE Chuang-ye, LI Xue-qin, PAN Bo, LIU Ying, LI Li-hua

The experiment was performed at the HI-13 tandem accelerator in the China Institute of Atomic Energy. The high spin states of 110Ag were populated via heavy-ion fusion evaporation reaction 110Pd(7Li, 2p2n)110Ag. The γ-ray from the evaporated residues were detected with an array consisting of fourteen Compton suppressed HPGe-BGO spectrometers. The beam energy was 49 MeV. The target consisted of 2.4 mg/cm2 thick Pd evaporated on a 0.4 mg/cm2 Au backing. More than 190×106 γ-γ coincidence events were collected. From the γ-γ coincidence analysis, a new level scheme of 110Ag has been presented. 110 The systematic features can be found by comparing the πg9/2⊗νh11/2 bands of Ag and its isotopes. 112, 114 First, signature inversion has been observed in the πg9/2⊗νh11/2 bands except Ag for lack of data. Second, the amplitude of signature splitting doesn’t change obviously among Ag isotopes as shown in Fig. 1. Third, the spin of inversion point decreases with increasing neutron number for Ag isotopes as shown in Fig. 2. Signature splitting is associated with the Coriolis force, and the amplitude of signature splitting increases with increasing Coriolis force. For the πg9/2⊗νh11/2 bands of Ag isotopes, proton Fermi surface locates at the top of g9/2 shell and neutron Fermi surface locates at the bottom of h11/2 shell. Therefore in this mass region neutron occupies small Ω orbital, the angular momentum of valence nucleon is almost parallel with the rotating axis and the Coriolis force is stronger, so the level gap of neutron in the h11/2 shell is very large, it is difficult to populate the unfavored state and the signature splitting of this band almost comes from proton in g9/2 shell. Therefore, the amplitude of signature splitting doesn’t change obviously among Ag isotopes.

Fig. 1 Signature splitting in 110Ag and its odd-odd isotopes □—102Ag；■—104Ag；○—106Ag；●—108Ag；◇—110Ag；◆—112Ag；△—114Ag；▲—116Ag

Considering that the j-Ω structure of the πg9/2⊗νh11/2 bands in the A≈100 region is very similar to that of the πh11/2⊗νi13/2 bands in the A≈160 mass region, we can expect a similar behavior of the spin of inversion point. In the A≈160 region the inversion spin behavior is explained with the competition FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 95

between Coriolis and the proton-neutron interactions. As in A≈160 region, similar explanation is suitable for A≈100 region. The neutron Fermi level increases with increasing neutron number resulting in the gaps between neutron Fermi surfaces and neutron Fermi surfaces to increase, so neutron-proton interaction decreases. Therefore, the spin of signature inversion decreases.

Fig. 2 Signature inversion in 110Ag and its odd-odd isotopes

* Supported by National Natural Science Foundation of China (10675171, 10105015, 10175070, 10375092,10575133), and Major State Basic Research Development Programme (2007CB815000)

Systematics of Shears Mechanism in A~110 Mass Region*

HE Chuang-ye, ZHU Li-hua, WU Xiao-guang, LIU Ying, WEN Shu-xian, LI Guang-sheng, Li Xue-qin, YANG Chun-xiang

Similar band structure has been found in odd-odd nucleus 104, 106, 108Ag[1-3], 108, 110In[4] and 102Rh[5] in A~110 mass region, they are all magnetic dipole bands. Their dynamic moment of inertia (J(2)) are smaller than the normal deformed band, such as band 4 in 130Ba[6], and even smaller than the super deformed band, in 152Dy[7], as shown in Fig. 1. The configuration of these dipole bands in 104, 106Ag, 108, 110In has been 2 reported as πg9/2⊗ν[h 11/2(g7/2/d5/2)] respectively. The level structure and de-excite pathways of the band 6 built on 12+ħ state in 108Ag[3] are very similar. The maximum angular momentum of band 6 in 108Ag observed in the experiment is 17ħ, this is consistent with the maximum angular momentum provided by 2 108 the configuration of πg9/2⊗ν[h 11/2(g7/2/d5/2)], these characters all suggest that band 6 in Ag probably has the same configuration as band 1 in 106Ag. (2) 2 It is shown in Fig. 1 that the dynamic inertia J of the bands with πg9/2⊗ν[h 11/2(g7/2/d5/2)] configuration increases with the proton number decreasing (it is a little larger only at low spin states of 96 Annual Report of China Institute of Atomic Energy 2007

104Ag). This is contributed from the increasing of collectivity. A same tendency is also displaying in Fig. 2. There is no signature splitting in Ag and in isotopes. But it is different for 102Rh, signature splitting enlarges to a certain extent with spin increasing. As we know, signature splitting comes from collective rotation. So the deformation of this band in 102Rh is larger than in Ag and in isotopes. As the increasing of collectivity, it leads to the character of shears mechanism disappearing in 102Rh. A conclusion can be drawn out from Fig. 1 and Fig. 2 that Ag isotopes probably attain the boundary of magnetic rotation at A~110 mass region.

Fig. 1 Dynamic momentum of inertia (J(2)) versus frequency (ω) ■—102Rh；●—106Ag；▲—108In；▼—104Ag；◆—108Ag；◄—110In；►—152Dy；★—130Ba

Fig. 2 Angular momentum as a function of rotational frequency for 102Rh, 104, 106, 108Ag and 108, 110In

References: [1] CHATTOPADHYAY S, et al. Phys Rev, 2004, C69: 044317. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 97

[2] DEO A Y, et al. Phys Rev, 2006, C73: 034313. [3] ESPINOZA-QUINONES F R, et al. Phys Rev, 1995, C52, 104. [4] CHIARA C J, et al. Phys Rev, 2001, C64: 054314. [5] GIZON J, et al. Phys Rev, 1999, C59: R570. [6] STUCH O, et al. Phys Rev, 2000, C61: 044325. [7] LAURITSEN T, et al. Phys Rev Lett, 2002, 88: 042501.

* Supported by National Natural Science Foundation of China (10675171, 10105015, 10175070, 10375092, 10575133), and Major State Basic Research Development Program (2007CB815000)

Study of Structure of High-Spin States in 112In*

LI Xue-qin, ZHU Li-hua, WU Xiao-guang, HE Chuang-ye, LIU Ying, PAN Bo, HAO Xin, LI Li-hua, WANG Zhi-ming, LI Guang-sheng, -yu1, WANG Shou-yu1, XU Qiang2, WANG Jian-guo2, DING Huai-bo2, ZHAI Jian3 (1 Peking University, Beijing 100871, China; 2 Tsinghua University, Beijing 100084, China; 3 Jilin University, Changchun 130023, China)

High-spin states in doubly odd nucleus have been study in A~100 mass region, there exists plenty of information of nuclear structure, for example, shape co-existence, band termination, magnetic rotations and so on. Handedness or chirality is a subject of general interest in molecular physics, elementally chiral doublet bands and optical physics. The occurrence of chirality in nuclear physics was suggested in 1997, and the predicted patterns of spectra exhibiting chirality, i.e., the chiral doublet bands were experimentally observed in 2001. Since the pioneer work on chirality in nuclear physics, much effort has been made to understand the new phenomena and explore their possible existence. Experimentally, chiral doublet bands have been identified in many nuclei in the A~130 mass region with the earlier suggested configuration －1 －1 πh11/2⊗νh 11/2, A~100 with πg 9/2⊗νh11/2. Adiabatic and configuration-fixed constrained triaxial relativistic mean field (RMF)[1] approaches are adopted in the A~100, and are indicted the favorable deformation β and γ for the ground states for chirality has been found in 102,108,110Rh,108-112Ag and 112In (γ ~30°,β~0.1), which implies that more chiral doublet bands can be expected in the A~100 mass region. In present work, the level structure and information in 112In is very few [2-5], the doubly odd nucleus 112In is selected as the object to investigate magnetic and chiral rotation bands. The high spin states of 112In have been populated via the 110Pd(7Li, 5n)112In reaction with a beam energy of 50 MeV at HI-13 tandem accelerator of China Institute of Atomic Energy，and studied by in-beam spectroscopic technique with a detector array consisting 14 BGO Compton-suppressed HPGe detectors. The target consisted of a 2.4 mg/cm2 of 110Pd enriched to 97.2 (±0.1)% and a 0.4 mg/cm2 of Au backing. A total of 1.9×108 γ-γ coincidence events were collected in the experiment in event-by-event mode in about 110 h beam time. After careful energy calibration and gain matching of each detector, the

γ-γ coincidence data were sorted offline into conventional Eγ-Eγ matrices. These matrices were analyzed by using the RADWARE package based on a Linux-PC system. By analyzing the γ-γ coincidence reactions and DCO ratios, A new level scheme of 112In including seventy-four new gamma transitions and six new bands has been presented, extended to 7 431 keV (Fig. 1). 98 Annual Report of China Institute of Atomic Energy 2007

Fig. 1 Level scheme of 112In from prensent experiment

Transition energies are marked in keV, the 188, 263, 187, 319 keV are known γ trasitions

References: [1] FRAUENDORF S, MENG J. Nucl Phys, 1997, A617: 131. [2] STAROSTA K, et al. Phys Rev Lett, 2001, 86: 971. [3] MENG J, PENG J, ZHANG S Q, et al. Phys Rev, 2006,C73: 037303. [4] EIBERT M, GAIGALAS A K, GREENBERG NI. J Phys G: Nucl Phys, 1976, 2: 12. [5] KIBEDI T, DOMBRADI Z, et al. Phys Rev, 1988, 37: 6.

* Supported by Major State Basic Research Development Program (TG2000077405), and National Natural Science Foundation of China (10175090, 10105015, 10375092, 10575092, 10575133)

Triaxial Shape in 129Ce*

LIU Ying, WU Xiao-guang, ZHU Li-hua, LI Guang-sheng, HE Chuang-ye, LI Xue-qin, PAN Bo, HAO Xin, LI Li-hua, WANG Zhi-min, LI Zhong-yu1, XU Qiang2, WANG Jian-guo2, DING Huai-bo2, ZHAI Jian3 (1 Peking University; 2 Tsinghua University; 3 Jilin University)

The experiment was carried out in the HI-13 tandem accelerator at the China Institute of Atomic FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 99

Energy. The high-spin states of 129Ce have been populated via heavy-ion fusion evaporation reaction 96Mo(37Cl, 1p3n)129Ce. The beam energy was 155 MeV and the target was of thickness 1.0 mg/cm2, mounted on a 19 mg/cm2 Pb backing. The γ-ray from the evaporated residues were detected with an array consisting of fifteen Compton suppressed HPGe-BGO spectrometers. More than 2.46×108 γ-γ coincidence events were collected. The lifetimes and quadrupole moments Qt have been extracted from the lineshape 129 analyses using DSAM. The deformation of the negative band of Ce was extracted from the Qt and JRR. At very high-spin and for member states of a rotational band the quadrupole transition moments depend only on the deformation parameters β and γ as 1/2 2 Qt=[3/(5π) ]ZeR β2cos(30°+γ)/cos30° Deformation should also be reflected in a variation of the collective moments of inertia, which depend on the quadrupole deformation parameters β and γ as

2 1/2 JRR=(2/5π)MR [1－(5/4π) β2cos(120°+γ)]

The lifetimes and quadrupole moments Qt have been extracted from the lineshape analyses using 129 DSAM. The deformation of the negative band of Ce was extracted from the Qt and JRR. It is concluded －1 2 that the g-deformation is about 0 degree after the backbending with JRR=51.02 MeV ·ħ and Qt = 4.127 eb.

Fig. 1 Relation between γ and β

* Support by National Natural Science Foundation of China (10675171, 10105015, 10175070, 10375092, 10575133), and Major State Basic Research Development Programme (G2000077405)

Dose Rate Effect on DNA Damage Induced by Heavy Ion*

KONG Fu-quan1, WANG Xiao1, NI Mei-nan1, SUI Li1,YANG Ming-jian1, ZHAO Kui1, 2 (1 China Institute of Atomic Energy, Beijing 102413, China; 2 School of Science, Hebei University of Technology, Tianjin 300130, China)

In course of irradiation the DNA damage may be influenced by dose, quality of rays, radio sensitivity and so on. In contrast with the low linear energy transfer (LET) rays, the heavy ions have come to people’s attention because of their high LET and Bragg peak in dose distribution, which can produce more 100 Annual Report of China Institute of Atomic Energy 2007

complicated track structure and induce badly damage on organisms, cells tissues and DNA. Some drugs can change the radio sensitivity. The dose rate is an important parameter too in the radiobiology. In this article, the purified plasmid DNA samples are irradiated by 37.3 MeV 7Li heavy ion at different dose rates. The distribution of DNA form is observed by the gel electrophoresis. The yield of SSB/DNA and DSB/DNA are gained with the theory equation. The qualitative explanation of dose rate effect in heavy ions irradiation is attempted. Fig. 1 shows the Gel electrophoresis image of DNA after irradiating by heavy ion 7Li at different dose rates of 65, 48.4, 25.8, 6.8 Gy/min from lane 2 to lane 5. Lane 1 is the control sample and the total irradiation dose is 500 Gy. Fig. 2 shows the fraction of DNA three forms after 7Li ion irradiation at different dose rates. The x-axis is the dose rate and the y-axis is the fraction of DNA forms. It is shown that the fraction of SC and OC in virtue of SSB decreases and the linear fragments induced by DSB increases as the dose rates decreases at the same dose. So the DNA is damaged seriously with the decreasing dose rates. When the dose rate decreases to the lowest dose rate of 6.8 Gy/min, the SC DNA disappears and smear lane appears in the linear fragments, which is sharp contrast to the result at the highest dose rate of 65 Gy/min.

Fig. 1 Gel electrophoresis image of DNA before and after 7Li ions irradiation at various dose rates

Fig. 2 Fraction of three forms of DNA before and after 7Li ions irradiation at various dose rates ■—B(OC)；●—D(L)；▲—F(SC)

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 101

It is shown that DNA is damaged more seriously and the yields of SSB and DSB per DNA increase with the decreasing dose rates because the reaction efficiency between DNA and heavy ions is improved. The dose rate has influence on yielding DSB more than on SSB for heavy ions since heavy ions had direct ionizing reaction on DNA apart from free radical, which can produce DSB easier. It is important significant for cancer therapy project by heavy ions and research of radiation biology.

* Supported by National Natural Science Foundation of China (10435020)

DNA Concentration Effect on DNA Radiation Damage Induced by 7Li Ion and γ-ray*

KONG Fu-quan1, WANG Xiao1, NI Mei-nan1, SUI Li1, YANG Ming-jian1, ZHAO Kui1, 2 (1 China Institute of Atomic Energy, Beijing 102413, China; 2 School of Science, Hebei University of Technology, Tianjin 300130, China)

DNA is considered to be the most important bio-macromolecule and target molecule responsible for all biological effects. During our former experiments, we adverted that the DNA strand breaks are related with DNA concentration. In this paper, the plasmid DNA samples are irradiated by 37.3 MeV 7Li ion and γ-ray with various DNA concentrations with scavenger (Mannitol) and without scavenger (Mannitol). The samples irradiated are analyzed by gel electrophoresis and alpha Innotech digital imaging system (Figs. 1-3). The distribution of DNA forms is observed and the yield of DSB/DNA is gained with the theory equation. The DNA concentration effect on DNA radiation damage induced by 7Li and γ-rays are discussed primary.

Fig. 1 Gel electrophoresis image of DNA after irradiated by γ-ray at various concentrations

Fig. 2 Gel electrophoresis image of DNA irradiated by 7Li ions at various DNA concentrations without mannitol 102 Annual Report of China Institute of Atomic Energy 2007

Fig. 3 Gel electrophoresis image of DNA irradiated by 7Li ions at various DNA concentrations with 600 mmol/L mannitol

The results show that DNA is injured more seriously as the DNA concentration decreases for both of 7Li ions and γ rays radiations. In the presence of mannitol, the yield of DSB/DNA induced by 7Li appears and increases with the decreasing DNA concentration, which is different from the disappearance of fragments irradiated by γ-ray. It indicates that the DSB induced by direct ionizing of heavy ion cannot be eliminated by means of scavenger. And the proportions of DSBs induced by free radical and direct ionizing is constant and is independent of DNA concentration when the DNA concentration is under some value, such as 50 ng/μL. These may be corresponding with the track structure of heavy ions, the probability of interactions as well as the conformation of DNA. Above results would be a challenge to the theoretic research and more and further experiments are needed.

* Supported by National Natural Science Foundation of China (10435020)

Investigation of Dose Effect of DNA Strand Breaks Damage Induced by Protons

SUI Li, ZHAO Kui, WANG Xiao, KONG Fu-quan, GUO Ji-yu, NI mei-nan, LIU Jian-cheng

Protons with high linear energy transfer (LET) values can depose more energies, local doses and have different ionizing track structure while through the matter comparing with the low-LET (such as X, γ-ray and electrons) radiation. Their complex ionizing tracks can produce DNA double strand breaks efficiently and more unrepaired damage, leading to cell killing, transformation or cancer and other higher relative biological effectiveness (RBE). It is important to study the mechanism of biological damage induced by protons and corresponding radioprotection at DNA molecular level. The results can provide the essential experimental data for the protons therapy and radioprotection for estimation of risk to crews and patients in case of exposure to high LET radiation, such as space or nuclear radiation environment. In this experiment, proton of 19 MeV generated by HI-13 tandem accelerator is scattered with Au target and dispersed with magnetic field of Q3D before passing the isolating valve sealed with Kapton foil fixed at the entrance of detector chamber in Q3D. Then the aqueous pUC19 plasmid DNA samples with or without free radical scavenger, mannitol irradiated evenly by the proton beam in air. The values of energy and corresponding LET are 16.4 MeV and 3.12 keV/μm at the entrance surface of the liquid sample. An Au-Si surface barrier semiconductor detector is set to monitor the irradiated doses during irradiation. Using the proton beam, the DNA samples without mannitol are irradiated with various doses（50, 100, 200, 300 and 650 Gy）at the same DNA concentration (20 ng/μL). The results analyzed by gel FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 103

electrophoresis show that DNA forms change from supercoiled to open circular (single strand break) and linear (double strand break). The supercoiled and open circular form is losing gradually as the dose increases, while the fraction of the linear DNA goes up and eventually approaches to one at higher doses. From the gel electrophoresis image, it is obvious that the open circular is the major form and a few linear forms exist at the dose of 50 Gy. At the dose of 200-300 Gy, the supercoiled form disappears and almost all forms are open circular and linear form. When the dose up to 650 Gy, all of DNA molecules are linear long and short fragments, which mean almost all DNA molecules occur double strand breaks. However， for the DNA samples with mannitol of 600 mmol/L under the same irradiating condition, the DNA molecules also occur single strand breaks, but the fraction much less than the DNA samples without mannitol. Moreover, the linear form is not exist at dose of less than 300 Gy，only at dose of 650 Gy, which suggest that mannitol can compete free radical with DNA molecule and scavenge the free radical generated during radiolysis, then reduce the yields of DNA single and double strand breaks induced by protons efficiently. Furthermore，the DNA samples with different concentration (10, 20, 40, 50 and 100 ng/μL) are irradiated at the same dose (50 Gy). The results show that the changes of DNA forms are affected by the concentration of DNA solution，including DNA samples with or without mannitol, which indicate that DNA single strand breaks become severe as the concentration decreases. This phenomenon suggests that the direct effect may be an important factor for the DNA stand breaks induced by protons. Another reason may be the number of free radical reacted with single DNA molecule increase as the concentration decreases.

Measurement Techniques for Low-Intensity Beam on HI-13 Tandem Accelerator

GUO Gang, CHEN Quan, HUI Ning, TENG Rui, JIANG Zhao, SHEN Dong-jun, LIU Jian-chen, CAI Li, WU Bin

Single event effect (SEE), induced when an energetic charged particle in natural space environment passes through the sensitive region of space-borne microelectronic device, can cause the on-orbit spacecraft running abnormal, more severely result in catastrophe. The problems associated with these effects become more severe as the feature size of microelectronic devices decreases. It is necessary that the ground simulation experiment based on the suitable accelerator be carried out to measure the curve of the SEE cross section versus linear energy transfer (LET) for heavy ion or energy for proton. Only the devices which ability of the SEE hardening meets the requirement can be used in the specific space application. The requirement on the energy and LET value of ion beam used in accelerator ground simulation experiment become more rigorous as the increasing on the anti-SEE hardening performance of devices. In order to obtain the higher energy ion beam under the condition of HI-13 tandem accelerator, it is feasible that the ion beam of high charge-state and heavier element be accelerated and used. Higher beam energy will be obtained, so is LET value, as higher charge-state is selected. However, at the same time the beam intensity will be decreased to pico-ampere or less. Therefore the diagnostics of low-intensity beam should be developed firstly. 104 Annual Report of China Institute of Atomic Energy 2007

Several scintillant materials commercially available such as ZnS(Ag), CaF2(Eu), CsI(Tl) etc. have been irradiated by 35Cl beam of 140 MeV and 197Au beam of 316 MeV under the different beam intensity. The experiment has been performed in the large chamber of heavy-ion microbeam irradiation facility which connected to HI-13 tandem accelerator. A CCD camera has been used to observe the beam imaging induced by ion strike on scintillator, and a pico-ampere meter has been used to measure the current induced by beam strike on Faraday cup. The techniques for in-situ measuring and displaying of low-intensity ion beam are proven to satisfy the requirement for tuning accelerator beam in SEE experiment, and will be used in future SEE experiment.

Scheme of Long-Distance Control for RS232 Serial Devices With New Beam-Line in Experimental Hall of HI-13 Tandem Accelerator

SHI Shu-ting, GUO Gang, HUI Ning, SHEN Dong-jun, LIU Jian-cheng, CHEN Quan, LU Xiu-qin

Single event effect (SEE) caused by space radiation is one of the important reasons for spacecraft malfunction. The new beam-line which we are constructing will be used for single event effect research. There are some RS232 serial devices in the new beam-line in hall II of the Tandem Accelerator National Laboratory, such as translation stage, electric shutters etc. In the process of experiment, in order to avoid an experimenter going into hall II so as to raise the efficiency of the experiment, we need to control these devices outside hall II. The long distant controlling configuration is depicted below, with an example of long-distance control of translation stage. The standard transmitting distance of RS232 signal is only 15 m. Because the distance from the translation stages to the control room is about 50 m, the translation stages can’t directly be controlled using common RS232 lines. There are two methods to prolong the deliver distance: 1) Add a RS232 signal extend driver on the deliver line (Fig. 1); 2) Convert the RS232 signal to other signal which can be transmitted farther. The first method is very easy to realize and it’s very economical, but it’s troublesomely to wire, and it’s difficult to add line when more RS232 devices be added in the measurement room later. The second method is better. The standard transmitting distance of the ether net signal is about 100 m. If we convert our RS232s signals to ether net signal, we can realize not only long distance controlling but also one line multi-platforms.

Fig. 1 Controlling translation stages by RS232 signal extend driver

In order to control the translation stages by the ether-net line, the simplest method is using two FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 105

computers, shown in Fig. 2.

Fig. 2 Controlling translation stages by two computers

In this configuration, computer A is just used as a server. Because we have several devices, we need to add serial cards for computer A. Thus the expenses will be very high. If we can find a kind of server which can convert RS232 signal to ether net signal, the problem will be solved. After investigation, we find a kind of multi-serial ports server which can be used in our experiment. There is a up-bound network port, 16 descending RS232 port on that server. It can make 16 RS232 device link to the ether net. We can link this device directly to the net card of computers (or internet), then some virtual RS232 port can be simulated by the software, thus each descending RS232 port has its own address and we can control each device respectively. And the price of this device is cheaper than a computer. From above, the long distance control scheme is: a computer is put in the measurement room and it is linked to the serial server by an ether net line. The translation stages controllers are linked to the serial server. Then the translation stages are linked to the controller. The advantage of that scheme is: There is only one ether net line between the measurement hall to the hall II, so it’s very convenient to wire. There are 16 RS232 ports on the serial sever. If the number of the translation stage is more than 16, we can add a HUB or SWICH on the ether net line and add a serial server.

Fig. 3 Controlling translation stages by a 16 serial ports server

This scheme has been successfully implemented in the proton experiment on the Q3D. In the later work, we are going to control the translation stages with LABVIEW to increase the efficiency of our experiments.

106 Annual Report of China Institute of Atomic Energy 2007

Etching Technique of Solid Nuclear Tracks Detector for Heavy-Ion Micro-beam Diagnostics

HUI Ning, GUO Gang, SHI Shu-ting, CAI Li, WU Bin

It is an effective method for studying the micro-mechanism of SEE that utilizes the heavy ion micro-beam with the spatial resolution comparable to the feature size of integrated circuit chips in ground simulation study. Important information can be obtained from micro-beam experiment to improve the performance of anti-SEE ability of integrated circuit chips. A new rectangular micro-collimator with an opening of less than 2 μm ×2 μm has been manufactured by orthogonally overlapping two pair of slits which are formed using two stainless steel blades with a surface roughness of less than 0.1 μm. Recently, some improvements have been done to enhance the performance of the heavy-ion micro-beam irradiation facility. It includes the development of laser orientation system, the reassembly of the long distant microscope positioning system, the sample stages, and so on. Therefore it is needed to make an experiment to measure the spot size of micro-beam. The 32S beam with energy of 48 MeV has been used in the experiment. When the beam passed the pinhole，We can use the beam monitor system and change the position and angle of pinhole to diagnose the beam, from which we selected the best beam to irradiate the solid trace detector. Then, the detectors have been etched chemically. We observe the trace distribution of ion through scan electron microscope to determine the dimension of micro beam and the function parameter of heavy-ion micro beam facility. The solid nuclear tracks detectors are polyester (PET) and CR-39. Because the size of pinhole is very small in this experiment, the size of ion track after etched should be fitted. If the size is too large, that will lead to overlap of the track. It is hard to be observed if the size is too small. If we will analyze the beam track statistically at the range of 2 μm×2 μm under the certain condition of ion irradiation quantity, we should control the diameter of single ion track around 0.1 μm. We should ascertain again the etching condition of PET we have been used before. Compared with PET, CR-39 which we have been used for the first time has some good characters such as it is hard to be abraded, easy to be marked and convenient to be observed, etc. We should ascertain the optimal etching condition through etching experiments.

Fig. 1 Image of PET on best etch condition Fig. 2 Image of CR-39 on the best etch condition Average diameter is 0.067 μm The diameter is approximately 0.1 μm

The optimal etching condition and SEM observe condition have been determined on the basis of a FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 107

great deal of etching work on PET and CR-39. The results are shown in Fig. 1, 2. At the same time, we have obtained the size of ion track on PET at different etching time and the same condition of lye concentration and temperature. The relationship is shown in Fig. 3. The results will be applied in future experiment to diagnosis micro-beam performance.

Fig. 3 Relationship between etching time and diameter of track

T1 Chamber in Heavy Ion Radiation Facility

CHEN Quan

A new beam line, heavy ion radiation facility (HIRF), will be built in 20° beam line of tandem accelerator lab. In the HIRF, there are 4 chambers, T1, T2, T3 and T4. The T1 chamber was described in this paper. The T1 is mainly for the beam diagnostics. After T1, beam goes through the bending magnet bending to the T2, T3 and sample chamber (T4). The T2 and T3 are for the beam diagnostics. There are quartz target, ZnS(Ag）target, Faraday cup, Au target, Si(Au) detector, CCD and shutter in the T1 chamber. The quartz target, and ZnS(Ag) target are for the beam monitoring. The beam image on the target is sent to control room for tuning the beam line. The ZnS(Ag) scintillator and the high sensitive CCD are enable to monitoring 1 pA beam image. The second feature of T1 is the measurement of the beam energy. It is important for the high charged beam, for example 197Au30+. There are many beam species in the high charged beam which have nearly the same magnetic rigid. So the beam energy spectrum analysis is very important for choosing the right beam. Beam energy measurements are performed using a 100 μg/cm2 Au target and a Si(Au) detector. The third feature of T1 is to reduce the beam current. A beam passing the Au foil, select a low possibility charge state is selected. Set the bending magnet only for this charge state. The beam intensity can be reduced 100 times. All the targets and Faraday cup are on a translation platform that can be controlled outside the chamber. The special instrument in T1 is an electronic shutter with 20 mm diameter at the entrance of this 108 Annual Report of China Institute of Atomic Energy 2007

chamber. This is demanded by the measurement of SEL. When a micro-chip SEL is detected, the shutter will cut down the beam within several ms, and the measurement system goes to there own program. After the chip is recovered, the shutter will open again. So the shutter is modulated by the measurement system. The T1 control system is at the control room and the measurement room.

Design of SRAM Testing System Based on Virtual Instrument Technology

TENG Rui, LIU Jian-cheng

The single event effects (SEE) threaten the reliability and life of semiconductor devices used to spacecrafts. So it is great significative and specific valuable to study the SEE of semiconductor devices. The design of SRAM SEE testing system is used to study single event upsets (SEU) and single event latch-up (SEL). The former testing systems used Single Chip Micyoco or FPGA technology. The ability of secondary development and functional expansion is very weak, so they cannot satisfy the actual application. Because virtual instrument uses data acquisition modulars, therefore simplifies the hardware circuits and saves the hardware resources. The developing software have excellent man-machine interface. The secondary development and functional expansion is very convenient, which saves the developing time greatly. In order to achieve new functions and requirement, it is only needed to change a bit of the program. So it can meet the need of different stages and different kinds of the SRAM test. The system uses PXI-6541 digital waveform generator/analyzer produced by National Instrument Company to test and count the SEU of SRAM, and programmable power supply E3634A by Agilent Company to monitor and count the SEL. Labview is used as the graphical computer language to program testing software.

Fig. 1 SRAM SEE testing system

There are two test panels of the system, that is initialization panel and testing panel. In the initialization panel, to the SEU test, it can initialize either of two SRAM, and any cell in the test board; to the SEL test, for the need of different SRAM test, it can set SEL threshold current and delay time. It also can choose the test mode, which is TIME, NUMBER and MANUAL. After initialization it can enter in FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 109

the testing panel. It can display and save the real-time number of SEU, MBU, 0→1 and 1→0. At the same time, it can also display and save the number, time and current value of SEL. Meanwhile the system can save test start time, end time, test time in the files set in advance, when something strange happens at test, if you want to stop the test ,you can do that or shut down the supply. When the test is over, it can exit the test software. The system is shown in Fig. 1. The correctness of the system was tested by man-made errors. It take less than 10 ms to test a 2K SRAM once, efficiency of SRAM is also satisfied. The system will be designed to compatible with 2K to 1M capability.

Experimental Study of Neutron-Neutron Quasi-free Scattering and Neutron-Neutron Final-State Interaction

RUAN Xi-chao, ZHOU Zu-ying, LI Xia, JIANG Jing, HUANG Han-xiong, ZHONG Qi-ping, TANG Hong-qing, QI Bu-jia, BAO Jie

The neutron-neutron (n-n) quasi-free scattering (QFS) and neutron-neutron final-state interaction (FSI) in the n-D breakup reaction at 25.0 and 17.4 MeV were investigated in this work. Firstly, the absolute cross section of n-n QFS in the nd breakup reaction at 25.0 MeV was determined with an accuracy of a few percent. The data were analyzed by detailed Monte-Carlo simulations based on modern realistic nucleon-nucleon (NN) potentials (CD-Bonn, Argonne ν18, Nijm I and II). The measured yield exceed the theoretical prediction based on CD-Bonn by (16.0±4.6)%. This result confirmed the discrepancy between experiment and theory in n-n QFS. Secondly, the absolute proton emission cross section was measured at around 0 degree in the n-D breakup reaction at 17.4 MeV with the kinematically incomplete configuration. The measured spectra were also analyzed by detailed Monte-Carlo simulations based on CD-Bonn, Bonn-B and Nijm I NN potentials. The n-n scattering length determined in this work is ann=－(16.81±0.63) fm.

Neutron Emission Double-Differential Cross-Section (DDX) Measurement of Natural Iron at 8.17 MeV Neutrons

RUAN Xi-chao, ZHOU Zu-ying, HUANG Han-xiong, LI Xia, ZHONG Qi-ping, TANG Hong-qing, JIANG Jing, CHEN Guo-chang, QI Bu-jia, BAO Jie, CHEN Lin

The experiment was performed with the fast neutron multi-detector time-of-flight (TOF) spectrometer at the HI-13 tandem accelerator. Three BC501A neutron detectors with the size of φ180 mm×100 mm were used to detect the scattered neutrons. The source neutron fluence was monitored with a small neutron detector during the experiment. Twelve angles of neutron emission spectra were measured. The flight path is about 6 m. The source neutrons were produced by D(d, n) reaction. The measured data were analyzed by detailed Monte-Carlo simulations to do the corrections for flux attenuation, multiple scattering, and finite geometry. The measured results were compared with the other measurements and the evaluated data. Fig. 1 shows part of the measured results.

110 Annual Report of China Institute of Atomic Energy 2007

Fig. 1 Measured results compared with other measurements and evaluated data a——Differential cross-section; b——DDX at 105°

Double-Differential Cross-Section Measurement of 9Be(n, xα) Reaction Induced by 14.8 MeV Neutrons

RUAN Xi-chao, CHENG Pin-jing, ZHOU Zu-ying, TANG Hong-qing, JIANG Jing, HUANG Han-xiong, LI Xia, HE Guo-zhu, CHEN Xiao-liang, ZHONG Qi-ping, XIN Biao, CHEN Guo-chang

The charged particle emission double-differential cross section (DDX) induced by fast neutrons is very important in nuclear engineering, model calculation and fast neutron cancer therapy. The α particle emission DDX of 9Be(n, xα) induced by 14.8 MeV neutrons was measured with a low pressure multi-wire proportional ΔE-E telescopes. The 14.8 MeV neutrons were produced via T(d, n)4He reaction at the CPNG neutron generator of China Institute of Atomic Energy (CIAE). The deuteron energy was 250 keV and a 1 mg/cm2 thickness of T-Ti target was used during the experiment. A large area and thick beryllium sample was used to enhance the event rate. The ΔE signals were produced by the multi-wire proportional chamber and a φ24 mm×0.8 mm CsI scintillator was used to detect the remaining energy of α particles. Three-fold coincidence of ΔE-ΔE-E and the pulse-shape-discrimination (PSD) of CsI detector were applied to identify the α particles. The neutron fluence was determined by counting the associated α particles of T(d, n)4He reaction, and the neutron fluence distribution along the target was determined by Monte-Carlo simulation and experiment. The measured data were analyzed by Monte-Carlo simulations and compared with the evaluated data and the theoretical calculation data with the LUNF code.

A Beam-Monitoring Time of Flight System With Plastic Scintillator*

QIN Xing1, WANG You-bao, WANG Bao-xiang, BAI Xi-xiang, GUO Bing, -hong, LIAN Gang, LIU Wei-ping, SU Jun, YAN Sheng-quan, ZENG Sheng (1 Normal University, Linfen 041004, China)

A beam-monitoring Time of Flight (TOF) system has been installed on the secondary beam line at the Beijing HI-13 TANDEM laboratory. The TOF system makes use of plastic scintillator coupled with FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 111

fast photomultiplier tube, and is intended for the identification of the secondary beam and for the determination of energy. Its performance was tested in a recent measurement of 1H(17F, p)17F elastic resonance scattering reaction[1].

Fig. 1 Time of flight spectrum of 17F secondary beam

The 17F secondary beam was produced via 2H(16O, 17F)n reaction. After collimated by a φ5 mm-3 17 mm collimator complex, the F beam impinged on a thick (CH2)n target to study the elastic resonance 1 17 17 scattering reaction H( F, p) F. The T1 and T2 detectors of the TOF system use foils of BC422 plastic scintillator with the thickness of 10 μm. The flight time spectrum of the 17F secondary beam is shown in Fig. 1. The peak value of 17F is 129.9 17 ns corresponding to 67.2 MeV. The remaining energy of F after passing the T2 detector is 60.0 MeV, which is in agreement with the value measured by the ΔE-E telescope. The ΔE-TOF scatter plot of 17F secondary beam is shown in Fig. 2, which shows the TOF-ΔE system is capable to discriminate the different particles in the secondary beam.

Fig. 2 ΔE-TOF scatter plot of 17F secondary beam

Reference: [1] WANG Youbao, WANG Baoxiang, BAI Xixiang, et al. A setup for resonance scattering reactions with thick target. High Energy Physics and Nuclear Physics, 2006, 30(Suppl.): 202-204 (in Chinese).

* Supported by National Natural Science Foundation of China(10445004, 10575136), and Major State Basic Research Development Program

(G2007CB815003) 112 Annual Report of China Institute of Atomic Energy 2007

13N+p Elastic Resonance Scattering via Thick-Target Method*

WANG You-bao, WANG Bao-xiang, QIN Xing, BAI Xi-xiang, GUO Bing, JIANG Chao, LI Yun-ju, LI Zhi-hong, LIAN Gang, SU Jun, ZENG Sheng, LIU Wei-ping

The advent of radioactive nuclear beam provides exciting opportunities to explore the new frontiers in nuclear physics and nuclear astrophysics. To use radioactive secondary beam of relatively low intensity, unique experimental methods and techniques have been brought forward to meet the challenges not encountered in the regular stable-beam experiments, the elastic resonance scattering in inverse kinematics with a thick-target is just one example. It uses an either solid or gas target containing hydrogen atoms, with a target thickness flexible to map a single level or a range of excited states. The recoil protons give rise to the excitation function of an energy interval corresponding to the energy loss of the incident beam. The advantage of this method is that one can obtain the excitation function in a one-shot experiment with an acceptable accuracy. Several secondary light-ion beams from 6He to 18F are available at the radioactive secondary beam facility of the HI-13 Tandem accelerator laboratory. The 13N secondary beam is among the ones with the best intensity. To extend our experimental researches towards to elastic resonance scattering, a proton ΔE-E telescope consisting of a 63 μm Double-Sided Silicon Strip Detector(DSSSD) and a 982 μm quadrant silicon detector(MSQ) was prepared and tested[1]. In thick-target resonant elastic scattering, since the 13N energy drops constantly along its trajectory, 14O is formed at various low-lying excited states, which promptly decay back into 13N+p with the 13N in its ground state. The 14O states above the proton threshold can therefore be surveyed for the missing 0－ level and for the supplement of other resonance parameters[2].

Fig. 1 Experimental excitation function for 13N+p elastic resonance scattering

The 13N+p elastic resonance scattering has been studied successfully in inverse kinematics via thick-target method. A 13N secondary beam of (47.8±1.5) MeV produced by the 2H(12C, 13N)n reaction 2 was used to bombard a 9.33 mg/cm (CH2)n target. The recoil protons were detected by the ΔE-E counter 13 telescope at θlab=15°. After careful analysis of the data, the excitation function of the N(p, p) elastic FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 113

scattering was obtained in the energy interval of Ec.m.=0.5-3.2 MeV, and was analyzed by using a multilevel R-matrix code MULTI7, see Fig. 1. Several low-lying excited states in 14O were revealed, our results confirm a very recent 2－ assignment to the 6.8 MeV level[3], and agree with the observation of a new 0－ level at 5.7 MeV in 14O with a slightly different width of 300(100) keV.

References: [1] WANG Youbao, WANG Baoxing. HEP & NP, 2006, 30(Suppl.II): 202(in Chinese). [2] AJZENBERG S F. Nucl Phys, 1991, A523: 1. [3] TERANISHI T, KUBONO S, YAMAGUCHI H, et al. Phys Lett, 2007, B650: 129.

* Supported by National Natural Science Foundation (10575136) and Major State Basic Research Development Program (2007CB815003)

Levels in 13N Examined by 12C+p Resonance Elastic Scattering via Thick Target Method*

QIN Xing1, WANG You-bao, WANG Bao-xiang, BAI Xi-xiang, GUO Bing, JIANG Chao1, LI Yun-ju2, LI Zhi-hong, LIAN Gang, SU Jun, ZENG Sheng, LIU Wei-ping (1 Institute of Modern Physics, Shanxi Normal University, China; 2 Institute of Physical Engineering, Zhengzhou University, China)

The conventional proton resonance scattering has been a powerful spectroscopic tool to explore the properties of compound nucleus levels close to the threshold, which is usually of astrophysical and structural significance. It is a kind of precise yet very time-consuming experiment, since one needs to change the proton beam energy in small steps in order to obtain an excitation function of the energy range of interest. To use radioactive ion beams with limited intensity and short lifetime, more efficient experimental method with the emphasis of inverse kinematics must be employed. For this purpose, the thick target method has been proposed and rapidly applied. It uses an either solid or gas target containing hydrogen atoms with thickness enough to stop the beam ions or degrade its energy to the region of interest. By measuring the lighter recoil particles at laboratory forward angles, one can rebuild the reaction kinematics taking account of the energy losses of particles in the target. The method allows one to study several resonances simultaneously by using a single bombarding energy of exotic beam. The method provides a way to effectively measure an excitation function with a one-short experiment, however, the complicity here is that at any individual angle, the proton energy spectrum is continuous over a certain range corresponding to the energy losses of particles in the thick target, therefore the detector system must have satisfactory angular resolution as the primary requirement. Prior to this work, a ΔE-E counter telescope has been developed consisting of detectors with large acceptance and high granularity. To check up the technique and the performance of the system, an experiment to 13 12 study the low-lying states in N was carried out using stable beam C and a thick (CH2)n target. The experiment was performed at the radioactive secondary beam line GIRAFFE of HI-13 Tandem accelerator laboratory, Beijing. The recoil protons were measured by the ΔE-E counter telescope based on a large area double-sided silicon strip detector at laboratory angles around θ0=15°. Good quality excitation function over a wide energy range of Ec.m=0.30-3.40 MeV has been obtained as shown in Fig.1 that demonstrates the capability of the technique. Levels in 13N were identified at 2.36, 3.50 and 3.55 MeV with deduced widths in good agreement with compiled values. The solid line in Fig. 1 was the fitting 114 Annual Report of China Institute of Atomic Energy 2007

calculation based on R-matrix theory with the resonance parameters taken from Ref. [1]. The theoretical curve agrees well with the experimental excitation function, indicating that the thick-target method can resolve the resonance levels with satisfactory accuracy.

Fig. 1 Experimental excitation function of 12C+p elastic resonance scattering

Reference: [1] AJZENBERG S F. Nucl Phys, 1991, A 523: 1

* Supported by National Natural Science Foundation of China (10445004, 10575136) and Major State Basic Research Development Program (G2007CB815003)

Production of 22Na Secondary Beam*

JIANG Chao1, LIAN Gang, WANG Bao-xiang, SU Jun, BAI Xi-xiang, ZENG Sheng, ZHENG Yong-nan, ZHU Sheng-yun, Zhu Li-hua, LIU Wei-ping, LI Zhi-hong, WANG You-bao, GUO Bing, QIN Xing1, LI Yun-ju2 (1 Institute of Modern Physics, Shanxi Normal University, Linfen 041004, China; 2 Institute of Physical Engineering, Zhengzhou University, Zhengzhou 450052, China)

22Na is an important radioactive nuclide involved in the explosive hydrogen burning process in stars, and is also the oftenest used β+-source in positron-annihilation spectroscopy. Its half-life is 2.6 a and is produced in novae (Clayton 1975).The study of the isotopic composition of meteorites has revealed some perplexing anomalies, in that the isotopic abundances of certain elements do not agree with the abundances of terrestrial material. Such anomalies include the presence of excess 129Xe, thought to be due to the decay of 129I, excess 26Mg, the daughter of 26Al, and the presence of almost pure 22Na, known as FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 115

Na-E. One theory is that 22Na is incorporated into the meteorite before β+  decaying to pure 22Na. If the 22Na was created in a neutron-rich environment, the (n, p) and (n, α) reactions may cause the destruction of 22Na before it could be incorporated into a meteorite. In the present experiment was performed by use of the secondary beam facility at the HI-13 tandem accelerator of Beijing. The 22Na ions was produced via 4He(19F,22Na)n reaction by bombarding a 4.8 cm long 4He gas cell at 1.6×105 Pa pressure with 100 MeV 19F ions .The front and rear windows of the gas cell were Havar foils, each in thickness of 1.9 mg/cm2. Because of 19F lose some energy at front window and He gas cell, the reaction energy of 19F is about 73.7 MeV in the middle of gas cell with the maximum angle 5.2° due to the inverse kinematics. After the magnetic separation and focus with a dipole and a quadruple doublet, the secondary beam was further purified with a wien filter. The main contaminants were 19F ions out of Rutherford scattering of the primary beam in the gas cell windows as well as on the beam tube. To reduce the angular divergence, the 22Na beam was collimated with two apertures 5 and 3 mm in diameter, then directed onto a ΔE-E counter telescope compose with a 19 μm thick silicon ΔE detector and a 300 μm thick silicon center E detector for particles identify at secondary chamber. The purity of the collimated 22Na beam is 57% after the magnetic and velocity selection. The beam energy is (52.9±1.93) MeV, the intensity is about 100 s－1. With the intensity of primary beam of 1 000 enA , the intensity of the 15O secondary beam is about 1 000 s－1. The energy spectrum of 22Na secondary beam and ΔE vs E scatter plot were show as Fig. 1.

Fig. 1 Energy spectrum of 22Na secondary beam (a) and ΔE vs E scatter plot (b)

* Supported by National Science Foundation of China (0575136) and National Natural Science Foundation of China (10605039)

Production of 6He Secondary Beam With High Purity*

LI Yun-ju1, LI Zhi-hong, GUO Bing, WANG You-bao, BAI Xi-xiang, SU Jun, LIAN Gang, ZENG Sheng, WANG Bao-xiang, QIN Xing2, JIANG Chao2, LIU Wei-ping (1 Institute of Physical Engineering, Zhengzhou University, China; 2 Institute of Modern Physics, Shanxi Normal University, China)

The proton capture reactions play an important role in the peculiar astrophysical sites which have the 116 Annual Report of China Institute of Atomic Energy 2007

high temperature and density. Many of these reactions are difficult to measure directly with currently available experimental techniques because the cross sections are very small and the available intensities of the radioactive ion beams are very low. In recent years, some cross section of the proton capture reactions and astrophysical S factors were deduced indirectly from the measurement of angular distribution for the transfer reaction at CIAE. 6He(p, γ)7Li is one of the important reaction in astrophysics. Its cross section and astrophysical S factor also can be obtained from the measurement of angular distribution for the 2H(6He, 7Li)n reaction. The eject nucleon of the 2H(6He, 7Li)n reaction is 7Li, and the main component in the 6He secondary beam is also 7Li, which will affect the measurement result severely. Therefore we must improve the quality of the 6He beam and take some effective methods to remove the affect from 7Li component. The experiment of production for 6He secondary beam was carried out at three energy of 7Li primary beam on the radioactive nuclear beam facility of the HI-13 tandem accelerator, Beijing. Finally, the 6He beam with the energy of 26, 32 and 38 MeV were obtained as shown in Fig. 1, the intensity of 320, 250, 450 s－1, and the purity of 63%, 84% and 95%, respectively. During the experiment, the φ5 mm-3 mm collimator complex was changed into the φ9 mm-5 mm －1 collimator complex at EHe=38 MeV. Then the beam was obtained with the intensity of 900 s , and the purity of 99%. The ΔE spectrums in two situation as shown in Fig. 2. The intensity and the purity is much improved in spite of the energy spread is increased as the collimators enlarge. And it also can be seen that the 6He and 7Li is identified clearly with one ΔE detector.

6 Fig. 1 ΔE-Et scatter plot of He secondary beam

Fig.2 ΔE spectrum of 6He beam with the energy of 38 MeV in two situation Diameter, mm：a——5-3；b——9-5 FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 117

In summary, the 6He secondary beam is obtained with the intensity of 900 s－1, and the purity of 99%, it could be used to measure the angular distribution of 2H(6He, 7Li)n.

﹡Supported by Major State Basic Research Development Program(2007CB815003) and National Natural Science Foundation of China(10675173)

Measurement of Angular Distribution for 8Li (p, d)7Li Reaction*

LI Yun-ju1, LI Zhi-hong, GUO bing, WANG You-bao, BAI Xi-xiang, SU Jun, LIAN Gang, ZENG Sheng, WANG Bao-xiang, QIN Xing2, JIANG Chao2, LIU Wei-ping (1 Institute of Physical Engineering, Zhengzhou University, China; 2 Institute of Modern Physics, Shanxi Normal University, China)

In recent years, significant efforts have been paid to the inhomogeneous big bang (IBBNs) and the r-process which synthesizes roughly half of all elements heavier than iron. 8Li (p, d)7Li is one of the key reactions involved in the reaction networks for the inhomogeneous Big Bang nucleosynthesis and for the seed-nuclide production of the r-process. In the IBBNs the stability gap at mass number A=8 can be bypassed with the reaction chains containing unstable nucleus 8Li to synthesize A>8 . Thus the IBBNs predict the relatively higher abundances for heavier nuclides in primordial nucleosynthesis than the standard model does. The production of A>8 nuclides depends on the abundance of 8Li during primordial nucleosynthesis. In the reaction networks of nucleosynthesis, 8Li is produced by 7Li(n, γ) and 7Li(d, p), and destroyed by its β decay as well as by the reactions such as 8Li(α, n)11B, 8Li(d, n)9Be, 8Li(d, p)9Li, 8Li(d, t)7Li, 8Li(d, α)6He, 8Li(p, d)7Li, 8Li(p, t)6Li, 8Li(p, α)5He, 8Li(p, nα)4He，8Li(p, γ)9Be and 8Li(n, γ)9Li. Most of these reactions have been measured in the past years. And the 8Li(p, d)7Li reaction is predicted to have large cross section and may be one of the main reactions to destroy 8Li. At low energies of astrophysical relevance, both the ground and first excited states of 7Li can be populated through this reaction due to the low excitation energy (0.477 MeV) of the first excited state in 7Li, and thus can contribute to destroying 8Li.

8 7 8 7 * Fig. 1 Total angular distribution of Li (p, d0) Li and Li (p, d1) Li at Ec.m.=4.0 MeV

118 Annual Report of China Institute of Atomic Energy 2007

We have measured the 8Li(p, d)7Li reaction leading to the ground and first excited state in 7Li by 8 using Li secondary beam at Ec.m.=4.0 MeV for the first time on the radioactive nuclear beam facility of the HI-13 tandem accelerator, Beijing. A set of ΔE-E telescope consisting of a 63 μm double sided silicon strip detector (DSSSD) and a 982 μm quadrant silicon detector (MSQ) was used to detect the production. 8 7 8 7 * Finally, the total angular distribution of Li(p, d0) Li and Li(p, d1) Li at backward angles is 8 7 obtained, as shown in Fig. 1. And The Li(p, d0) Li contribution accounts for 40%-58% in the mixture angular distribution through fitting the total energy spectrum.

* Supported by Major State Basic Research Development Program(2007CB815003) and National Natural Science Foundation of China(10675173, 10705053)

12 11 γ-ray Spectroscopy of ΛC and ΛB

FU Yuan-yong, ZHOU Shu-hua, T. Koike1, S. Kinoshita1, Y. Ma1, Y. Miura1, K. Miwa1, Y. M i y a g i 1, K. Shirotori1, T. Suzuki1, H. Tamura1, K. Tsukada1, M. Ukai1, K. Futatsukawa1, K. Hosomi1, M. Kawai1, M. Mimori1, N. Terada1, N. Maruyama1, K. Aoki, H. Fujioka, Y. Kakiguchi, T. Nagae, D. Nakajima, H. Noumi, T. Takahashi2, T. N. Takahashi2, A. Toyota2, M. Dairaku3, T. Fukuda4, S. Minami4, W. Imoto4, S. Ajimura5, K. Tanida6 （1 Department of Physics, Tohoku University, Sendai, 980-8578, Japan; 2 High Energy Accelerator Research Organization (KEK), Tsukuba, Ibaraki, 305-0801, Japan; 3 Department of Physics, Kyoto University, Kyoto, 606-8502, Japan; 4 Osaka Electro-Communication University, Osaka，572-8530, Japan; 5 Department of Physics, Osaka University, Osaka, 560-0043, Japan; 6 RIKEN, Wako 351-0198, Japan）

12 11 The purpose of this Λ C and Λ B γ-ray experiment is to cross-check the experimentally determined spin-dependent ΛN interaction parameters, and try to understand the difference theoretic prediction and 10 experiment results in the energy gap between the Λ B ground state doublets by measuring the 12 corresponding ground state doublet of Λ C , and test the possibility by using the life-time measurement of 11 ＋ ＋ the Λ B (7/2 →5/2 ) M1 transition to infer the magnetic moment of the Λ particle in nuclear medium. The experiment was carried on at K6 beam line (KEK) with the γ-ray spectrum-Hyperball2. The efficiency of Hyperball2 is 5% for γ-ray at the 1.33 MeV after add-back, and the energy resolution is about 5.3 keV. A 20 cm polyethylene target(with intensity of 18.6 g/cm2) has been used in this experiment. And we also use a 2 cm carbon target as reference target. Total 1.3×1012 π+ hit the polyethylene target. We have observed three γ-ray in this experiment:

12 − − Λ C ： E γ ( 12 → 21 )=(2 667.3±2.8) keV 11 + + Λ B ： E γ (1/2 →5/2 )=(1481.7±0.7) keV 11 + + Λ B ： E γ (7/2 →5/2 )=(261.6±0.24) keV 11 ＋ ＋ In this experiment, we assigned the 261.6 keV γ-ray to the Λ B (M1(7/2 →5/2 )) transition, which was not assigned in previous experiment E518. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 119

With these 3 γ-rays, we extracted two new parameter values of ΛN two body interaction (Δ and SN). − − From Eγ（12 → 21 ）=(2 667.3±2.8) keV, we get SN＝－0.7 MeV. ＋ ＋ From Eγ（1/2 →5/2 ）=（1481.7±0.7) keV, we get SN＝－0.9 MeV. ＋ ＋ From Eγ（7/2 →5/2 ）=（261.6±0.24) keV, we get Δ＝0.33 MeV. 11 ＋ ＋ Since the M1 transition energy of Λ B (7/2 →5/2 ) is smaller than theoretical result, we are not 11 able to get the information of the magnetic moment of Λ in Λ B . Due to the poor statistics, we didn’t 12 observe the transition between the Λ C ground state doublets.

A Method of Evaluating Discrepant Data

HUANG Xiao-long, WANG Bao-song

Several methods of evaluating discrepant data are introduced and compared each other briefly. The advantage and disadvantage of these methods (WM: weighted mean, LRSW: Limitation of relative statistical weights, MBAYS: Modified Bayesian Technique, NR: Normalized Residuals, and RA: Rajeval technique) are outlined. On the basis of these analysis and comparison, a new method, i.e., Double-Mean method of evaluating discrepant data was proposed. The Double-Mean method (DM) takes into account the experimental uncertainties of different authors and all the available experimental information is fully considered. Thus the evaluated values of DM are less dependent on discrepant data and the uncertainties of the evaluated values are more reliable, i.e., the deviation between the evaluated results and the “true” values smaller than the other evaluation methods. The application of using the measured half-life and γ-emission probability for 7Be is given as an example. The results of half-life and γ-emission probability deduced from the present work are

T1/2=(53.282±0.012) days and Pγ=(10.45±0.04)%, respectively.

Theoretical Analysis of n+6Li Reactions and Establishment of Neutron Data Libraries at Incident Neutron Energy Below 20 MeV

WANG Ji-min, ZHANG Jing-shang

The cross section and the double-differential neutron emission cross section data of light nuclei are very important in the nuclear engineering design and neutron shielding design. However, the absence of the double-differential cross section files in international neutron evaluation libraries is an open problem, due to lack of usable theoretical approach. The new light nuclear reaction theoretical model could solve these problems well. The cross section data for neutron induced reactions on 6Li are the prime requirements of the design of breeding blankets for D-T fueled thermonuclear reactors. Tritium is produced by the 6Li(n, t) reactions, the consumption of tritium for nuclear fusion reactors will be compensated exactly with the improvement of the data veracity of the tritium producing. The double-differential cross sections for 6Li are given in CENDL-3.1, but the improvement is needed to neutron data libraries of 6Li with the updated level 120 Annual Report of China Institute of Atomic Energy 2007

schemes related with the n+6Li reactions, such as 6Li, 5He, 5Li. So the double-differential cross sections of total outgoing neutrons for n+6Li reactions have been calculated by using the updated LUNF code, the calculated results agree fairly well with the measurements at incident neutron energies of 8.17, 10.286, 11.5, 14.2 and 18 MeV. Thus, based on the full fitting the neutron data libraries including the 6 double-differential cross sections file for Li at En≤20 MeV have been established.

Establishment of Double Differential Cross Section File for 10B at Incident Neutron Energy Below 20 MeV

WANG Ji-min, ZHANG Jing-shang

The double-differential cross section data of light nuclei are very important in the nuclear engineering design and neutron shielding design. However, the absence of the double-differential cross section files in international neutron evaluation libraries is an open problem, due to lack of usable theoretical approach. The new light nuclear reaction theoretical model could solve these problems well. By using the new light nuclear reaction theoretical model, the complete nuclear data for neutron induced 10B reactions at incident neutron energies below 20 MeV have been calculated, while the neutron data libraries including the double-differential cross sections file for 10B have been established. The double-differential cross sections files of 10B are absent in CENDL. So the double-differential cross sections of total outgoing neutrons for n+10B reactions have been calculated, by using the new reaction model for light nuclei, with the updated level scheme and the new optical model parameters, which agree fairly well with the measurements at En=14.2 MeV. Therefore, based on the full fitting the 10 neutron data libraries including the double-differential cross sections file for B at En≤20 MeV have been established.

Establishment of Double Differential Cross Section File for 11B at Incident Neutron Energy Below 20 MeV

WANG Ji-min, ZHANG Jing-shang

The new light nuclear reaction theoretical model based on the unified Hauser-Feshbach and exciton model have been formed. By using the new reaction model for light nuclei, the complete nuclear data for neutron induced 11B reactions at incident neutron energies below 20 MeV have been calculated, while the neutron data libraries including the double-differential cross sections file for 11B have been established. The double-differential cross section data of light nuclei are very important in the nuclear engineering design and neutron shielding design. However, the absent of the double-differential cross section files in international neutron evaluation libraries is a open problem, due to lack of usable theoretical approach. The new light nuclear reaction theoretical model could solve these problems well. The double-differential cross sections files of 11B are absent in CENDL. So the double-differential cross sections of total outgoing neutrons for n+11B reactions have been calculated, by using the new reaction model for light nuclei, with the updated level scheme and the new optical model parameters, which agree fairly well with the measurements at En=14.2 MeV. Therefore, based on the full fitting the FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 121

11 neutron data libraries including the double-differential cross sections file for B at En≤20 MeV have been established. The file-6 has been given in the eighth release of American ENDF/B-VI library by using the Kalbach systematic. However, the Kalbach systematic formula is only suitable to calculate the double-differential cross sections of the continuous state emissions of the first emitted particles. For emission processes from compound nucleus to the discrete levels of the residual nuclei, the smooth spectrum shape is given by using the Kalbach systematic simply, meanwhile the energy balance is not held. The comparison of the file-6 of 11B between the neutron data libraries established by using the new light nuclei reaction model and ENDF/B-VI library by using the Kalbach systematic are performed. The results indicate that the double-differential cross sections of total outgoing neutrons by the new reaction model for light nuclei agree fairly well with the measurements.

5He Emission in Neutron Induced 11B Reactions

WANG Ji-min, ZHANG Jing-shang

The possibility of 5He cluster emission for neutron induced light nucleus reaction has been affirmed theoretically. As well known, 5He is unstable and separated into a neutron and an spontaneously. The neutron spectra from 5He breakup process contribute to the low energy region of the total outgoing neutron double-differential cross sections, and the calculated results could improve the fitting with the double-differential measurements. In addition, the calculated results show the fact that the 5He cluster is emitted mainly from the pre-equilibrium emission process in n+11B reactions. In n+11B reactions, 5He cluster emission has been discussed with the updated level scheme and the new optical model parameters. In this paper the reaction channels related to 5He emission are listed in detail. By using the new reaction model for light nuclei, the double-differential cross sections of total outgoing neutrons 11 for n+ B reactions at En=14.2 MeV have been calculated, which agree fairly well with the double-differential measurements. The comparisons of the double-differential cross sections of total outgoing neutrons for n+11B reactions between considering 5He emission and without 5He emission are shown at En=14.2 MeV for each outgoing angles, respectively. Particularly, in the energy-angular spectra the contribution from the 5He -emission to the total outgoing neutron double-differential cross sections has also been analyzed. To show the contribution from the 5He-emission the partial energy-angular spectra of o 5 60 at En=14.2 MeV have been given. Indeed, once the He emission is taken into account, the fitting with the double-differential measurements of total outgoing neutrons at the low energy region could be improved. Therefore, to consider the 5He emission properly in the reaction processes of light nuclei is necessary.

Theoretical Calculation of n+28Si Reaction Below 20 MeV

ZHANG Hua

Based on detailed benchmarks for 28Si data of CENDL-3.1, neutron current leakage spectra with 122 Annual Report of China Institute of Atomic Energy 2007

CENDL-3.1 are much lower in 4-8 MeV, and the photon current leakage spectra is nearly lower 66% than the experimental one. New evaluation data about 28Si was calculated by using UNF, APMN and DWUCK code system. The new evaluation has many improvements compared with the one of CENDL-3.1. Cross sections of some reactions are more reasonable, elastic scattering and direct inelastic scattering angular distributions and double differential spectra show better agreement with the experimental data than CENDL-3.1. Neutron and photon leakage current spectra are better than CENDL-3.1 with energy 3-8 MeV. Some results are shown in Figs. 1-4.

Fig. 1 Comparison of experiment data and other evaluation data

for calculated En=14.1 MeV elastic scattering distribution

Fig. 2 Comparison of experiment data and other evaluation data for calculated elastic scattering cross section FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 123

28 Fig. 3 Comparison of experiment data and other evaluation data for calculated En=14.2 MeV Si(n, xn)

Fig. 4 Comparison of experiment data and other evaluation data for calculated neutron current leakage spectrum

Benchmarks for 28Si Evaluation Data of CENDL-3.1

ZHANG Hua

The benchmark testing is carried out for neutron current leakage spectra and photon current leakage spectra from 28Si of CENDL-3.1 by using Monte-Carlo code, and the calculated results from CENDL-3.1, JENDL-3.3, JEFF-3.1 and ENDF/B-VII.0 are compared with experimental one. From the benchmark test results, it can be seen that the neutron current leakage spectra with CENDL-3.1 are much lower in 4-8 MeV, and the photon current leakage spectra is nearly lower 66% than the experimental one. It is necessary to improve on the cross sections of some reactions, double differential spectrum, and photon 124 Annual Report of China Institute of Atomic Energy 2007

production data of 28Si from CENDL-3.1.The new neutron evaluation for 28Si has been done based on these results, and the benchmark testing for new one shown in the following figures. The result is very good (Figs. 1, 2).

Fig. 1 Comparison of experiment data and other evaluation one for calculated neutron current leakage spectrum with 28Si

Fig. 2 Comparison of experiment data and other evaluation one for calculated photon current leakage spectrum with 28Si

Benchmark Testing for 14N Evaluation of CENDL-3.1

WU Hai-cheng, DUAN Jun-feng

The validation of 14N evaluation for preliminary CENDL-3.1 was performed with neutron angular flux experiment FNS. The angular fluxes based on evaluated library CENDL-2.1, 3.0, 3.1b0, ENDF/B-VII.0 and JENDL-3.3 were calculated and compared with measurement[1-4]. The analysis shows the overestimation of the inelastic cross section from discrete energy level. Then, a revised evaluation with FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 125

the inelastic cross sections substituted by those from JENDL-3.3 was proposed (Fig. 1). Further testing shows the elimination of the over prediction of the angular flux between 6-8 MeV. However, the underestimation of (n, np) and some other secondary particle emission cross sections are to be improved in future.

Fig. 1 Comparison of angular neutron flux

References: [1] OYAMA Y, MAEKAWA H. Angular neutron flux spectra leaking from slabs, JAERI-M 94-014. 1994. [2] OYAMA Y, KOSAKO K, MAEKAWA H. Measurements and analyses of angular neutron flux spectra on liquid nitrogen. Liquid Oxygen and Iron Slabs at Int'l Conf on Nuclear Data for Science and Technology. Juelich, 1991. [3] CHADWICK M B, OBLOZINSKY P, HERMAN M, et al. ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology. Nuclear Data Sheets, 2006, 107(12): 2 931-3 060. [4] SHIBATA K, KAWANO T, NAKAGAWA T, et al. Japanese evaluated nuclear data library. Version 3: JENDL-3.3. J Nucl Sci Technol, 2002,11: 1 125-1 136.

Benchmark Testing for Silicon Evaluation of CENDL-3.1

WU Hai-cheng

The validation of Si evaluation for CENDL-3.1 was performed with neutron and gamma leakage current experiment OKTAVIAN[1-2]. The leakage current based on evaluated library CENDL-2.1, 3.1, ENDF/B-VII.0[3] and JENDL-3.3[4] were calculated and compared with the measurement. Under prediction of inelastic scattering cross section from discrete energy level of 28Si, the missing of gamma emission information from (n, p) and (n, α) and overestimation of elastic scattering cross section around 14 MeV were observed through analysis (Figs. 1, 2). 126 Annual Report of China Institute of Atomic Energy 2007

Fig. 1 Comparison of neutron leakage spectra

Fig. 2 Gamma leakage spectra comparison

References: [1] CHIHIRO I, KATSUHEI K, SHU A H, et al. Leakage neutron spectra from various sphere piles with 14 MeV neutrons, JAERI-M 94-014. 1994. [2] YAMAMOTO J, KANAOKA T, MURATA I. Gamma-ray energy spectra emitted from spheres with 14 MeV neutron source, JAERI-M 94-014. 1994. [3] CHADWICK M B, OBLOZINSKY P, HERMAN M, et al. ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology. Nuclear Data Sheets, 2006, 107(12): 2 931-3 060. [4] SHIBATA K, KAWANO T, NAKAGAWA T, et al. Japanese evaluated nuclear data library, Version 3: JENDL-3.3. J Nucl Sci Technol, 2002, 11: 1 125-1 136. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 127

Benchmark Testing for 16O Evaluation of CENDL-3.1

WU Hai-cheng

The validation of 16O evaluation for CENDL-3.1b0 was performed with neutron angular flux experiment FNS[1]. The angular fluxes based on evaluated library CENDL-2.1[2], 3.0, 3.1b0, ENDF/B-VII.0[3] and JENDL-3.3[4] were calculated and compared with measurement. The contributions to the angular fluxes from the elastic scattering, inelastic scattering and (n, nα) reaction are analyzed in detail. The results show that the cross sections for the above reaction channels are to be improved (Figs. 1, 2).

Fig. 1 Comparison of leakage neutron angular fluxes calculated based on CENDL-2.1, 3.1b0 and JENDL-3.3

Fig. 2 Comparison of leakage neutron angular fluxes calculated based on ENDF/B-VII.0, CENDL-3. 0 and 3.1b0

128 Annual Report of China Institute of Atomic Energy 2007

References: [1] OYAMA Y, MAEKAWA H. Angular neutron flux spectra leaking from slabs, JAERI-M 94-014. 1994. [2] TINGJIN L. The present status of CENDL-2.1, NEA/NSC/WPEC/DOC 139, 1996. [3] CHADWICK M B, OBLOZINSKY P, HERMAN M, et al. ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology. Nuclear Data Sheets, 2006, 107(12): 2 931-3 060. [4] SHIBATA K, KAWANO T, NAKAGAWA T, et al. Japanese evaluated nuclear data library, Version 3: JENDL-3.3. J Nucl Sci Technol, 2002, 11: 1 125-1 136.

Application of TALYS Code in Study of Mass Distributions of Fission Fragment

CHEN Yong-jing, LIU Ting-jing

The TALYS code is a new nuclear model code which is based on the temperature-dependent multi-channel random-neck rupture model and has been developed to describe the mass distributions of fission fragment and fission product. TALYS is the only microscopic code which can describe the fission yields in 1 keV-200 MeV energy range. The TALYS code has been installed and applied in this work. The calculated mass distributions of fission fragment agree well with the experimental data by adjusting the corresponding parameters properly. The mass distribution of fission fragment of 235U has been studied in this work using TALYS code. This kind of study is important for further theoretical study and evaluation of mass distribution of fission fragment, as well as the energy dependent of fission yields and the theoretical study of post fission behavior. Moreover, the TALYS code has been extended, the method to calculate the average prompt neutrons from fission yields and the prompt neutrons as a function mass have been developed.

Research on Prompt Neutron Multiplicity Distribution of Fission Fragment

CHEN Yong-jing, LIU Ting-jing

A new method to calculate the prompt neutron number as a function of the mass of fission fragments was developed based on the pre-neutron and post-neutron mass distributions calculated with the TALYS code. The distribution of the average number of emitted neutrons from fission fragments depends on how the available total excitation energy is distributed among the light and heavy fission fragments, and this is a long-standing question. In the present work, we have considered splitting the available total excitation < > energy by linking to experimental values for ε (A) and Eγ ()A . Under this assumption, we find a reasonable agreement with experimental Eγ ()A distribution.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 129

Introduction and Application of TALYS Code

TAO Xi, GE Zhi-gang

The main work is implementing and applying TALYS code. TALYS code, mainly developed by A. J. Koning of the Nuclear Research & Consultancy Group (NRG), is based on optical model, Hauser-Feshbach theory with width fluctuation correction, two-component exciton model, coupled-channels method, and so on. TALYS can be used to calculate the nuclear reaction that induced by neutrons, gamma-rays, protons, deuterons, tritons, 3He and alpha-particles, with a wide incident energy range (0.001-200 MeV) and mass number range (12

Calculation of Neutron-Induced Reaction on 181Ta Below 30 MeV

TAO Xi, GE Zhi-gang

In this work, TALYS is used for calculating reaction data of neutron with 181Ta. Based on the experiment data of total, elastic cross section and elastic scattering angular distributions for n+181Ta, a set of neutron optical model potential parameters is obtained in the region of incident neutron energy from 0.1 to 30 MeV. Using this set of OMP parameters, the total, elastic cross section and elastic angular distributions are calculated in the region of incident neutron energy from 0.1 to 30 MeV. Furthermore, the results from this work are compared with the evaluated data from ENDF/B6, JENDL-3.3, ENDL-2.1 and related experimental data. It shows that the total, elastic cross section and elastic angular distributions from this work are all in good agreement with the experimental data, and some improvements compared with the evaluations of ENDF/B6, JENDL-3.3 and ENDL-2.1 are obtained. Especially, the cross sections of reactions (n, n’), (n, γ), (n, 2n) and (n,3n) are in good agreement with experiment data, and better than those in ENDF/B6、JENDL-3.3 and CENDL-2.1. The cross sections of charged particles emission channels are in good agreement with experiment data, by adjusting OMP parameters of charge particles. In addition, the energy spectra and double-differential spectra agree with experiment data, too.

Theoretical Model Calculations of n+58,60,61,62,64Ni With EMPIRE Code

QIAN Jing, GE Zhi-gang

The goal of this work is to give the theoretical calculated results of n+58,60,61,62,64Ni with EMPIRE program. 130 Annual Report of China Institute of Atomic Energy 2007

Based on experimental data of total reaction cross sections, elastic scattering cross sections and elastic scattering angular distributions of n+Ni and its isotopic nucleus, the detail calculations and analyses were performed on all cross sections of neutron induced reaction, the elastic scattering angular distributions, the cross sections and inelastic scattering angular distributions of discrete levels, double differential cross sections of neutrons emission as well as neutron energy spectrum by using a set of suitable neutron optical potential and related parameters selected from the Reference Input Parameter Library-2 (RIPL-2) in the region of incident neutron energy below 20 MeV. The calculated results of present work are not only compared with the experimental data but also compared with other evaluated data from ENDF-BVII, JENDL-3.3, JEFF-3.1 and CENDL-3.0. It shows that the present results are reasonable and agree well with experimental measurements, especially in double differential cross sections of neutrons emission.

Exploitation of Nuclear Reaction Model Code EMPIRE-2.19

QIAN Jing, GE Zhi-gang

EMPIRE code system is an important code which can be used for the projectile of any nucleon or heavy ions with a very broad energy region (0-200 MeV). The code has many model theories for nuclear reactions and could output many results. Besides, the EMPIRE code system provided many benefits such as the convenient connection with the Reference Input Parameter Library-2 (RIPL-2) and EXFOR, the friendly interface and the short run time. Present work finished introducing of the EMPIRE code system to Chinese Evaluated Nuclear Data Library (CENDL) of China Nuclear Data Center (CNDC) and achieved the flow of the calculations and the plotting capabilities. Meanwhile, we give the remarks which will help to avoid problems when running the EMPIRE code. It is expected that the improvement of CENDL will be achieved in nuclear reaction model code system and evaluation method by this work.

Development of a Thickness Measurement Set Using α Energy Loss

DU Ying-hui, HU Yue-ming, ZHOU Jian-ming

The alpha particle energy loss is a useful method to determining foils’ thickness. We established a set using alpha particle energy loss to measure foils’ thickness and uniformity. It is composed of vacuum system, position movement system, and alpha spectrometer and calculate program. Fig. 1 shows the details of the measurement chamber. In order to increase the measurement accuracy, we divide the foil into more than 20 layers to calculate the thickness by computer, the total thickness of the foil was obtained by summing thickness of every layer. Fig. 2 shows the thickness versus number of layers. Several foils have been measured by this set, the result compare with balance weight (Table1). FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 131

Fig. 1 Measurement chamber

Fig. 2 Thickness versus number of layers

Table 1 Measurement result

Foils Balance weight/(mg·cm－2) α-energy loss/(mg·cm－2) Accuracy/% Cu 7.23 6.97 3.6 Cu 3.3 3.19 3.3 Cu 1.97 1.95 1 Cu 1.09 1.13 3.7 Al 2.3 2.4 4 Al 1.25 1.3 4 Al 0.71 0.8 12 Au 1.18 11.1 1

Design and Debug of a New Foil Stretcher for Plunger Targets

FAN Qi-wen, WU Xiao-guang, PAN Bo

This report describes a foil holder and stretching technique that allows easy, reliable production of good quality stretched foils for recoil-distance lifetime measurements that they need to be able to position 132 Annual Report of China Institute of Atomic Energy 2007

the two foils at a distance of some micrometers down to one micrometer without contact. The foil tension is obtained by compression of an “O”-ring in contact with the foil, which is thereby stretched over an stainless steel tube, one end of which has been optically polished.

1 Foil stretcher for plunger targets and mounting or debug of the foils The new foil stretchers are illustrated schematically in Fig. 1. Fig. 2 is a photograph of a disassembled stretcher, and Fig. 3 shows two stretched foils, one target and one stopper. The stretching technique relies on the compression of an “O”-ring between two surfaces; that of the mount itself and the lower surface of the tapered ring (Fig. 1a). The foil is first carefully placed over this “O”-ring, as flat as possible, and the tapered ring then carefully lowered onto it. Four screws are then inserted into holes in the ring, and screwed into the mount; these screws are easily visible in Fig. 3. They should be tightened until there is no more slack, but not so tight that the foil cannot easily slide between the “O”-ring and the tapered ring. When that is done, a stretching tube (Fig. 1c) is pushed up the center of the mount and clamped there with three screws. This tube pulls the foil up into a shallow truncated cone, and lifts the flat part of the foil (across the top of the tube) above the surface of the ring. The top of the tube is optically polished to provide a flat planar stretching surface; the quality of this polish and the cleanliness of the surface, together with the quality and cleanliness of the foil to be stretched, finally determine the quality of the stretched foil that can be obtained. Finally, the four screws are slowly and evenly tightened clamping the foil against the “O”-ring. As the “O”-ring gets compressed, the foil is drawn down and stretched across the polished surface of the tube. If they are over-tightened, the foil will of course break, but it is easy to obtain good stretching for the flat part of most foils before this happens. Indeed, for Al and Au foils of 2-10 mg/cm2, a success rate of virtually 100% can be achieved.

Fig. 1 Schematic drawing of foil stretchers

Fig. 2 Photograph of a disassembled stretcher FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 133

Fig. 3 target stretched foils (left) and stopper stretched foils (light)

2 Preparation of 209Bi/Au and Pb/Au plunger foils The good quality stretched 209Bi/Au and Pb/Au foils have been prepared. The Au foils of 2-10 mg/cm2 are first carefully obtained by rolling, and then are mounted on the stretcher by the methods mentioned above, but they can not be compressed over-tightened, because during the evaporation of 209Bi and Pb, the “O”-ring will be expanded due to baking. 209Bi and Pb are then deposited on the Au plunger foils by resistance heating under the condition, that the evaporating distance is 10 cm, so the “O”-ring can not be destroyed due to baking. Finally, the four screws are slowly and evenly tightened clamping the foil against the “O”-ring.

Progress of Neutron Residual Stress Instrument Project at CARR

LI Jun-hong, LI Ji-zhou, HAN Song-bai, GAO Jian-bo, YU Zhou-xiang, ZU Yong, LIU Rong-deng, LIU Xiao-long, LIU Yun-tao, CHEN Dong-feng

The neutron residual stress instrument project at the China Advanced Research Reactor (CARR) went well in 2007. The main work was listed as follows. Firstly, we contacted with the manufacturers of position sensitive detector, acquired the specification parameters of different products. According to the designed performance parameters of the residual stress instrument, we selected a detector which met the demand and configured correlative components for it. Finally the design proposal of detection system was completed. Secondly, in reference to the geometry of the instrument and the needed wavelength range, we decided the dimension of monochromator and the reflecting crystal plane. We completed the design proposal of double focused Si monochromator. Thirdly, we contacted with the manufacturers of stages which were used for placing the monochromator and preliminarily accomplished the conceptual design. Fourthly, we repaired the damaged cards in the electronics system, purchased some new hardware for the system and compiled program for them. Fifthly, we signed the design and manufacture contracts of monochromator shielding drum with a company in Beijing. They had completed the conceptual design of the shielding drum. At present, the shielding drum was in the machining operation stage. We also confirmed the specification of dense concrete and building section.

134 Annual Report of China Institute of Atomic Energy 2007

Diffraction Measurements of Residual Stress in High Tension Steel by Neutron

LI Jun-hong, LI Ji-zhou, HAN Song-bai, GAO Jian-bo, LIU Yun-tao, CHEN Dong-feng

Residual stresses in a body are those which are not necessary to maintain equilibrium between the body and its environment. The macro stresses just described are of type Ⅰ because they vary continuously over large distances. This is in contrast to residual stresses which vary over the grain scale (typeⅡ or intergranular stresses) or the atomic scale (type Ⅲ). The presence of residual stresses in engineering components can significantly affect their mechanical property. It is generally agreed that compression stresses are of benefit to enhance the fatigue resistance of components. However, tensile stresses produce adverse effect to components because maybe they will impel to the crack dehiscence, stress corrosion and decrease fatigue life. The academe and industry have thanked much of researching residual stress since long time. It would be hoped to know the state of residual stress and the effect on performance in the metal components. Because it is difficult to forecast the residual stress, proper measurement of them is very important. The large penetration depth of neutron makes it a powerful tool in determining the magnitude and distribution of the residual stress non-destructively. In a stressed specimen, lattice spacing are altered and a shift in each Bragg peak position occurs, then the elastic strains are given by ε=Δd/d =－Δθ×cot θ (1) Strains in three mutually orthogonal directions r, θ, z are converted into stresses using Hookes Law by ε: E σ =−++⎡ ()1 νε νε ( ε )⎤ θθ()()112+−νν⎣ rz⎦ E σ =−++⎡ ()1 νε νε ( ε )⎤ (2) rrz()()112+−νν⎣ θ ⎦ E σ =−++⎡ ()1 νε νε ( ε )⎤ zzr()()112+−νν⎣ θ ⎦ The sample is a high tension steel with column shape, its diameter is 16 mm, length is 110 mm. At the sections which the distances from the top surface are 45, 50, 55 mm, respectively, we measured the residual stresses in three directions.

Progress in High Resolution Powder Diffractometer at CARR

LI Mei-juan, SUN Kai, JIAO Xue-sheng, XIAO Hong-wen, HAN Wen-ze, LIU Yun-tao, CHEN Dong-feng, ZHANG Bai-sheng

The high resolution powder neutron diffractometer (HRPD), which designed by ourselves and manufactured by local companies, will be located at thermal neutron double-beam tube at China Advanced Research Reactor (CARR). At present, the project goes smoothly under schedule. As one of the most important components of HRPD, the detector system comprises a set of 64 FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 135

collimators/counters with interval 2.5º, 64-channel electronic device and detector shielding. The 3He proportional counters, which record neutrons respectively at different angle position, were delivered to CIAE in June 2007. Both stability and dimension are very important to 64-channel electronic device. We not only need to assure each signal from different channel could not be interfered each other, but also consider the size according to the spatial array of HRPD. So in our design project, every five amplifiers and discriminators were integrated together in a NIM slot, but 64 preamplifiers were made independently. The device will be finished in June 2008. The shielding for multicollimator/detector was made of high density polyethylene with 10% boron. We have finished mechanical design, and signed the manufacture contract in this year. It is predicted that the shielding will be delivered in February 2008. The vertical focused monochromator is another important component for the diffractometer. Here, It will be used that the hot pressured Ge(115) wafer which developed by Neutron Scattering Laboratory of China Institute of Atomic Energy (CIAE). From the neutron and X-ray diffraction data of Ge wafers, it was showed that the rocking curves had a good Gauss distribution and the horizontal mosaic was nearly 17′, which can meet our demand. Furthermore, mosaic the vertical focusing bracket for fixing mosaic Ge crystals have been accomplished. The first collimator and monochromator are arranged in a direct neutron beam outside horizontal tubes of CARR reactor. In order to shield neutrons and gamma rays, one-meter thickness heavy concrete with density over 5.0 g/cm3 will be built around the first collimator and monochromator. For such huge shielding, it must be divided into many small blocks. So many factors should be considered carefully when we design it, such as weight of each block, reliability of joint and the monochromatic neutron beam tube arrangement. Up to now, we have completed the mechanical designing. At same time, the installation, adjustment and test of the diffractometer at CARR are being considered, we hope that the HRPD can be run when the CARR reactor is critical, and we can do day-1 experiments when the stable neutron beam is served.

Repair and Mend of Controlling System of Neutron Residual Stress Diffractometer

YU Zhou-xiang, LIU Yun-tao, LI Ji-zhou, LI Jun-hong, LIU Xiao-long

A neutron residual stress spectrometer which will be used to measure stress is planned to be made in neutron scattering project of CARR. In order to save time and money, some components of spectrometer are imported from R2 reactor of Sweden. These components include XY flat stage, Z flat stage, and rotary stage of detector, Euler Cradle, ω rotary stage and groups of circuit boards for controlling movement of these components. The mechanical property of imported components is good, but the control software is not graphical interface and is not easy to operate because it was developed long time ago. Therefore, new control software is decided to be developed. Since the imported groups of circuit boards of components were built for a long time, they become too old and some of them can not work normally. On the one hand, we try our best to repair them and use substitutes to replace the broken parts which can not be repaired; on the other hand, we plan to construct new moving control system independently. Currently, for the software, we have programmed control software which has graphical interface using virtual instrument language LabWindows/CVI; for the hardware, we have repaired the broken groups of circuit boards successfully, and master the technique of constructing new moving control system which has good expansibility and 136 Annual Report of China Institute of Atomic Energy 2007

could fully replace the imported one. The moving control system which has 8 axes with high precision has been achieved.

Monte-Carlo Simulation for Neutron Monochromator Shielding

JIAO Xue-sheng, SUN Kai, LIU Yun-tao, CHEN Dong-feng

According to the demands of neutron scattering instrumentation, especially high resolution powder diffractometer (HRPD) and high intensity powder diffractometer (HIPD), to be built at China Advanced Research Reactor (CARR), the primary design of the shielding for HRPD and HIPD has been done. Moreover, the shielding effect is simulated using MCNP4C, a widely used Monte-Carlo simulation code. The simulation results have provided essential data for the designs. HRPD and HIPD will share a thermal neutron double beam tube, so both of monochromator shielding would be considered together. Here, the simulation process is divided into two steps. Firstly, according to the known neutron data before the rotated doors, the shielding effect is calculated by Monte-Carlo method when both of doors are closed. It is shown that the shielding is not enough, and it is necessary to add a 30 cm thick heavy concrete shielding wall with a density of 5.0 g/cm3. Secondly, the simulation result at the exit of rotation door which is opened is used as source data to simulate the monochromator shielding. After simulating, the result shows that the primary design is enough to radiation safety protection; furthermore, the thickness of shielding can be reduced at some position. Finally, the optimized design for the shielding has been offered after thinking over the layout of CARR hall, the demands of instrumentation and the simulation results. In order to improve Monte-Carlo sampling and solve deep penetration problem, multi-step method and geometry splitting with Russian roulette are used.

Simulation and Optimization on Polarized Neutron Reflectometry

LIU Rong-deng, CHENG Zhi-xu, LIU Xiao-long, LI Tian-fu, LIU Yun-tao, CHEN Dong-feng

A polarized neutron reflectometer, used for the study of structure of film, will be constructed at China Advanced Research Reactor in China Institute of Atomic Energy (CIAE). The polarized neutron reflectometer is high costly. To complete the construction of instruments effectively and economically, at present, the design parameters of instruments are usually simulated and optimized using Monte-Carlo method in the world. Some parameters of key components of the reflectometer are simulated and optimized by VITESS (Virtual Instrumentation Tool for European Spoliation Source), which is written for European Spoliation Source by Hahn-Meitner-Institute. The height, curvature radius and tilting angle of the vertical focusing monochromator, the size of the slits, the integral intensity at sample position and instrumental resolution were determined. These results will give an important support to the design of the polarized neutron reflectometer to be built in CIAE. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 137

Study on Thermal Expansion Property of Molybdates Er1.6Cr0.4Mo3O12

WU Mei-mei, LI Jun-hong, HAN Song-bai, LIU Yun-tao, CHEN Dong-feng, CHENG Ying-zhi1, 1 1 1 PENG Jie , XIAO Xiao-ling , HU Zhong-bo (1 College of Chemistry and Chemical Engineering, Graduate University of Chinese Academy of Sciences)

Materials with controllable thermal expansion coefficients (TEC) can be widely used in aerospace materials, engine parts, integrated circuit boards, optical substrates and so on. It was reported that Er2Mo3O12 exhibits pronounced negative thermal expansion (NTE) with the linear TEC of －6.14×10－6 ℃－1 in the ranbe of 200 ℃ to 800 ℃ temperature range, and Cr2Mo3O12 shows positive thermal expansion with TEC of 4.54×10－6 ℃－1 using dilatometer in the temperature range of RT to 800 ℃ . It is thus possible to make the 3+ 3+ TEC of Er2－xCrxMo3O12 controllable by partial substitution of Er with Cr .

Molybdates Er1.6Cr0.4Mo3O12 was synthesized by conventional solid-state reaction. Stoichiometric ratio of Er2O3, Cr2O3 and MoO3 were fully ground together and calcined at 850-900 ℃ . XRD data for

Er1.6Cr0.4Mo3O12 at 200, 400, 600 and 800 ℃ were collected on PAN X' Pert PRO MPD with Cu Kα radiation (λ=0.154 06 nm) at Beijing Normal University. The XRD patterns were refined using the Rietveld software, FULLPROF. －6 －1 The linear TEC of compound Er1.6Cr0.4Mo3O12 was calculated to be －5.85×10 ℃ in the

200-800 ℃ temperature range, which is larger than that of Er2Mo3O12. That is to say, the NTE behavior of 3+ 3+ Er2－xCrxMo3O12 is weakened with the substitution of Er with Cr . If molybates Er2－xCrxMo3O12 with higher Cr3+ content can be synthesized, zero thermal expansion compounds is expected to be obtained. Further research is now in progress.

Preparation and Related Measurements of Silicides of Rare Earth Metals

R5Si3(R=Pr, Nd, Tb, Dy, Ho, Er) Compounds

ZU Yong, HAN Wen-ze, LIU Yun-tao, SUN Kai, DU Hong-lin1 (1 Magnetic Laboratory, Physics Department of Peking University)

The R5Si3(R=Pr, Nd, Tb, Dy, Ho, Er) compounds were synthesized from high purity starting materials by arc melting under Ar atmosphere. The samples were remelted several times to insure homogeneity and heat treated at 1 325 K. X-ray diffraction was carried out to determine the crystallographic structure and phase components. It is found that the annealed sample had better single phase than the unannealed. The crystal structures of R5Si3 were refined by Riveted method. It is revealed that Pr5Si3 and Nd5Si3 belong to tetragonal system and crystallize in space group I 4/mcm. The patterns of

R5Si3 (R=Tb, Dy, Ho, Er) can be quite well indexed in the hexagonal system with space group P 63/mcm. Because the rare earth atoms occupy two different crystal sites, the magnetic interaction is very complicated. The susceptibility versus temperature curve of Dy5Si3 was measured by the equipment of Peking University. It indicates that it forms antiferromagnetic structure and the Neel temperature is 125 K. Under the Neel temperature, the relation of the susceptibility and the temperature is very complex. For

DyxEr5－xSi3, It is not possible to ascertain the occupation of Dy atom. Although the samples had been 138 Annual Report of China Institute of Atomic Energy 2007

measured by X-ray diffractometer, we needed further neutron diffraction data to distinguish those sites because Dy and Er are adjacent elements, which X-ray scattering factors are similar. In future, we will validate our supposition by the two methods and analyze the magnetic structure by neutron diffraction.

Relocation of Neutron Instruments From Juelich Research Center in Germany

TIAN Geng-fang, WU Zhan-hua, CHENG Zhi-xu, YANG Hao-zhi, LIU Yun-tao, CHEN Dong-feng

The Neutron Scattering Laboratory of Department of Nuclear Physics will continue its neutron scattering research at China Advanced Research Reactor (CARR). International collaboration will accelerate the instruments construction, save costs, be beneficial to the technical reservation and talent training. Neutron triple axes spectrometer (TAS) and four circle diffractometer (FCD) are basic instruments in neutron scattering research. So it’s planned to import two FCDs and a newly commissioned TAS from Forschungszentrum Jülich GmbH, Germany (FZJ). Both sides signed the cooperation agreement based on the instruments in the December, 2007 and the instruments relocation is going on smoothly. The TAS was developed by FZJ from 2001 to 2005 and the two FCDs have been working over 20 a and got fruitful achievements in crystal structure research. Because the reactor of FZJ shut down on May, 2nd 2007, all neutron instruments beside the reactor will be transferred to other neutron sources. The scientists between China Institute of Atomic Energy (CIAE) and FZJ have long-term traditional collaboration in neutron science, and both sides have the intension to strengthen the relation starting from the instruments relocation. Neutron instrumentation expert Dr. Harald Conrad from FZJ came to CIAE to consult the dancing floor, air pad, instrument control and electronic system in March, 2007. The air pads had been transport to CIAE in August, 2007, which will be used as a standard tool to check to the quality of dancing floor together with a sample tower to simulate the actual running environment. The mechanical part of FCDs had been disassembled, examined and repaired by FZJ. The result shows that the mechanical accuracy is as good as the international mainstream neutron instruments. The electronic components will be upgraded and reassembled before transferred to China. Neutron Scattering Laboratory started to design the shielding, monochromator and collimator system. The three neutron instruments will be the first phase instruments at CARR and will be powerful tools for all neutron users from China and other countries.

Progress of Simultaneous Measurement Method

DOU Yu-ling1, HE Ming, TUO Fei2, JIANG Shan （1 College of Physics Science and Technology, Guangxi University, Nanning 530004,China; 2 School of Nuclear Science & Technology, University, Lanzhou 730000, China)

The ratio of the radioisotopes to the stable isotope is the final result for AMS measurement. So, the FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 139

beam current of stable isotope and the counts of rare radioisotopes are the important values in AMS measurement. In order to get higher precision, the sequential injection method has been developed in CIAE AMS system. Two off-set Faraday cup has been settled after the inject magnet. When the detector counted the , the off-set Faraday cup can be used to measure the stable isotopic. The range of off-set Faraday cup movement is from 25 to 75 mm. So, ions with M/ΔM (ΔM is the mass difference of the radioisotopes and its stable isotope) from 22 to 64 can be measured in this way. During our 36Cl measurement, this method is checked. The result is shown in Fig. 1. I (off-set cup) is the average beam current measured with off-set Faraday cup during a long time accumulation. I (F3-cup) is the beam current measured with the center Faraday cup. This means that the off-set Faraday cup can measure the current correctly and the high precision can be achieved.

Fig. 1 Curve of beam comparison

AMS Measurement of “In-Situ Produced Cosmogenic” 10Be in Loess Quartz from Luochuan

DOU Yu-ling1, LIN Min, HE Ming, TUO Fei2, LI Chao-li, JIANG Shan （1 College of Physics Science and Technology, Guangxi University, Nanning 530004, China;

2 School of Nuclear Science & Technology, , Lanzhou 730000, China)

Loess is the most important and the most typical continental clastic sediments of Quaternary. So the measurement of “In-situ produced cosmogenic” 10Be is expected to be used for the loess stratigraphic age. But the production rate of in-situ produced cosmogenic 10Be in loess quartz is very low. It requires very high sensitivity and accuracy of measurement. This work is to measure “In-situ produced cosmogenic” 10Be in loess quartz in Luochuan with the HI-13 AMS system at China Institute of Atomic Energy (CIAE). In order to achieve the high precision, the simultaneous measurement method was used. The AMS measurement results of 10Be samples are listed in Table 1. The measurement of “In-situ produced cosmogenic” 10Be can provide basis for the ratio of 26Al/10Be which can provide the bury age of different layer.

140 Annual Report of China Institute of Atomic Energy 2007

Table 1 AMS measurement results of 10Be samples

Sample N(10Be)⁄ n(9Be) 10Be content/g－1

L8 (2.52±0.60)×10－13 （8.40±2.02）×106

L9 (1.73±0.42)×10－13 （5.77±1.37）×106

Note: Results are normalized by the standard sample SRM 4325(n(10Be)⁄n(9Be)=2.68×10－11)

Application of Bragg Curve Detector for Heavy Nuclear Measurements in AMS

LI Chao-li1, WANG Wei, HE Ming, WU Shao-yong, JIANG Shan, RUAN Xiang-dong1 (1 Physics Science and Engineering Technology Department, Guangxi University, Nanning 530004, China)

A Bragg curve detector was improved and its schematic layout was showed in Fig. 1. Its best working condition was tested and performance is reported in the paper. The resolution of the detector is 0.9% for alpha particle at 5.486 MeV from 241Am source, and the Bragg peak signal resolution is 1.2%, each ΔE signal resolutions with the shaping time 1, 2 and 3 μs is 0.7%, 0.5% and 0.5% respectively, corresponding to cathode- grid reduced filed of 0.25 V/(cm·Torr－1) and grid-anode reduced filed of 2.5 V/(cm·Torr－1) in P10 gas.

Fig. 1 Schematic layout of Bragg curve detector

Its application in AMS measurements for heavy nuclear isobaric identification is firstly improved and some heavy nuclear like 36Cl, 79Se were measured at China institute of Atomic Energy (CIAE) AMS Bean Line. For AMS measurement of 36Cl standard sample, the detector energy resolution achieved was 1.2% and the Bragg peak resolution was derived to be 2.13%. The Bragg peak signal spectrum was showed in 36 36 Fig. 2. The figure of merit S=(ＥB( Cl)－ＥB( Si))/ΔE(FWHM) of Bragg peak and ΔE1 with shaping time of 1 μs is 2.0 and 3.13 respectively. These value is equivalent to ΔE3 and Eγ of CIAE-AMS multi-anode chamber. For AMS measurement of 79Se standard sample, with the accelerator terminal voltage of 8.4 MV and charge state of 11+, a energy of 104.3 MeV 79Se bean was obtained. The detector energy resolution achieved was 1.2% and the Bragg peak resolution of 2.13% was obtained. This detector can partly FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 141

79 79 separate Se from its isobar Br by using the two dimensional spectra of Bragg peak versus ΔE1 which is showed in Fig. 3.

Fig. 2 Spectra of Bragg peak for measurement of 36Cl standard sample using CIAE-AMS Bragg curve detector (a) and 36 projection spectra of Bragg peak versus ΔE1 for Cl standard sample (b)

36 Fig. 3 Spectra of Bragg peak versus ΔE1 for AMS measurement of Cl standard sample using CIAE-AMS Bragg curve detector a—Blank sample；b—Standard sample

At energy of 1.2-2 MeV/u, this Bragg curve detector can identify isobaric 36S from 36Cl in AMS 142 Annual Report of China Institute of Atomic Energy 2007

measurement. As the range signal can not be obtained from the Bragg curve detector, so its result was partly separate 79Se from its isobar 79Br. If the range signal can obtained through electronics, the Bragg curve detector would have a better performance, and it bring a good dominance for the application of Bragg curve detector for heavy nuclear measurements in AMS.

Preliminary Research on Measurement of 126Sn by AMS

SHEN Hong-tao, HE Ming, WANG Xiang-gao, SHI Guo-zhu1, WANG Wei, LI Chao-li1, TUO Fei2, DOU Yu-lin1, ZHANG Da-wei1, HUANG Chun-tang1, WU Shao-lei, HE Guo-zhu, WU Shao-yong, JIANG Shan (1 College of Nuclear Science & Technology, Lanzhou University, Lanzhou 730000, China; 2 College of Physics Science and Technology, Guangxi University, Nanning 530004, China)

The tin isotope 126Sn is a long-lived beta-particle-emitting radionuclide with half-life of (2.30±0.14)×105 a. Artificially produced 126Sn has entered our environment through nuclear weapons testing and releases from reprocessing plants and may locally lead to strongly enhanced 126Sn concentrations. So the long half-life of 126Sn may have implications on the nuclear pollution in our environment. Further more, in supernova explosions 126Sn is predominantly produced by rapid neutron capture (γ-process). The live 126Sn observed in primitive meteorites can imply that some live nuclear material was resent at an early stage of the solar system formation. But the primary difficulty in the determination of the 126Sn concentration is the interference of the stable isobar 126Te. AMS is one of the most important methods to detect minute amounts of 126Sn. This experimental works were carried out － using the HI-13 tandem accelerator at CIAE national lab, SnF3 ions from the negative ion source were injected into the accelerator whose terminal voltage is 8.7 MV. Sn10+ ions were selected by an analyzing magnet and finally were counted individually using ΔE-E gas ionization detector. A preliminary result of sensitivity of 126Sn/Sn atomic number ratio=1.2×10 － 8 has been obtained. It still needs further experimental works to be done for the AMS measurement of 126Sn.

Method of 236U Measurement With AMS and Its Applications

WANG Xiang-gao, WANG Wei, HE Ming, SHEN Hong-gao, LI Chao-li1, TUO Fei2, SHI Guo-zhu1, DOU Yu-lin1, Zhang Da-wei1 , HUANG Chun-tang1, HE Guo-zhu, WU Shao-yong, JIANG Shan (1 College of Nuclear Science & Technology, Lanzhou University, Lanzhou 730000, China; 2 College of Physics Science and Technology, Guangxi University, Nanning 530004, China)

Uranium occurs naturally in the Earth’s crust and in seawater, at around 2.7×10－6 m and 3.0×10－6 b, 236 respectively. The radionuclide U has a long half-life T1/2=23.4 a, it is produced via neutron capture on 235U. 236U does occur in nature but only a ultra-trace concentrations, with a ratio 236U/238U atom of 10－14[1]. The enhanced level of 236U is potentially as a “fingerprint” of irradiated uranium for nuclear safeguards or other applications. It is very difficult to measure the content of 236U with routine methods. Accelerator Mass Spectrometry (AMS) may be the best method to measure ultra-trace 236U with high sensitivity[2]. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 143

Measurement of isotopic ratios of 236U can monitor the nuclear activities or fuel burn-up in emissions from reprocessing facilities, and give information on nuclear physics research. The AMS group from China Institute of Atomic Energy are doing research on the 238U(n, 3n)236U cross sections of neutron induced reactions around 14 MeV. In order to obtain the best molecular ion species, we test the uranium oxide, carbide and fluoride’s negative ions from sputter sources. The yield of the negative ion, suppressing the interfering molecular isotopic and the transmission efficiency are taken into account, we choose the UO－ as the sample form.

Besides, UO2 samples mix of Nb, Ag, and Al with different mass ratio are tested. The result shows that the beam current was the largest when sample mixes of with the mass ratio 1:1, and the beam current was stable during the long-working time. The radionuclide 236U is difficult to transmit in AMS measurement for so heavy ion. We successful 236 － 208 － transmit UO beam by using PbO2 beam to simulate transmission. Fig. 1 shows the isotope components obtained by electrostatics deflector, and Fig. 2 shows the TOF vs. energy spectrum. The preliminary results shown that the background level is 236U/238U (atom ratio)=2.2×10－9, this work supply the basis for the further application by using 236U.

Fig. 1 Isotope components obtained by electrostatics deflector

Fig. 2 Spectrum of TOF vs energy

References： [1] MARSDEN O J, LIVENS F R, DAY J P, et al. The ANALYST. 2001, 126: 633-636. [2] CHRISTOF V R, et al. International Journal of Mass Spectrometry. 2003, 223-224: 713-732. 144 Annual Report of China Institute of Atomic Energy 2007

An Ultra-sensitive Method for Quantization of 79Se to Be Used as Environmental and Biological Tracer Isotope via Accelerator Mass Spectrometry

WANG Wei, HE Ming, JIANG Shan, WU Shao-yong, LI Chao-li1, TUO Fei2, WANG Xiang-gao, SHI Guo-zhu1, ZHANG Da-wei1, HUANG Chun-tang1, SHEN Hong-tao (1 College of Nuclear Science & Technology, Lanzhou University, Lanzhou 730000, China; 2 College of Physics Science and Technology, Guangxi University, Nanning 530004, China)

5 Selenium-79 (T1/2=2.80×10 a) which decays by pure β-minus emission, is chemically and radiological toxic. It is mainly produced in nuclear reactors and can only be found at significant levels in spent nuclear fuel and in waste materials resulting from fuel reprocessing. Because of its potential migration ability to the environment by leaching/dissolution and then transport by flowing groundwater, 79Se is considered as an important radionuclide for the management of nuclear waste disposal sites. The concept is based on protecting humans and the natural environment from both radioactive and chemically toxic contaminations of the waste. Furthermore, selenium which has a narrow concentration range between deficient and toxic levels in the diets of human and animals is an essential trace element to humans, animals and some plants and related with lots of diseases, such as heart disease, cancer, hepatitis, diabetes as well as AIDS. Formerly, Se and 75Se (gamma emitter) were used as 79Se analogs to estimate the high mobility and bio-kinetic of 79Se which there is no efficient ways to quantify with high sensitivity. Due to the potential analysis need and application of selenium-79 in environmental science and biomedicine, the method for quantization of 79Se in environmental and biological samples is very significant. Only accelerator mass spectrometry (AMS) which is a nuclear physics analytical technique with high sensitivity for quantization of rare long-lived isotopes can determine such ultra-trace levels of 79Se. The method below would make it possible that 79Se can be used as environmental and biological tracer isotope for long time observation and research owing to its long half-life and weak radioactivity. The procedure of experiment is followed.

1 Transmission of ion beam

The blank and series standard samples of Ag2SeO3 prepared previously along with silver powder with a molecular scale of 2:1 were pressed into aluminum cones with 1 mm diameter respectively, and then the target plate into which all the aluminum cones were mounted would be baked at 70 ℃ for 24 h in the automatic electric oven, before it was put into the MC-SNICS (Multi-Cathode Source of Negative Ion － by cesium sputtering) ion source. We extracted SeO2 negative ions. Typical parameters used for the detection of 79Se on HI-13 AMS system are a tandem voltage of 8.9 MV and a charge state q=11+ owing to the deficient deflection ability , which is produced with a probability of only 4% by a carbon stripper foil in the terminal. The total transmission efficiency is about only 0.6%. The particle was accelerated to the energy of 104 MeV and then entered into electrostatic analyzer with a 7×4 slit in the back. Afterwards, the particle entered into the multi-anode ΔE-E detector filled with 110 mbar P10 gas. The beam current of 80 － 80 SeO2 which can be converted to the counts of Se was measured by faraday cup in the image focus of the injection magnet, while 79Se counts was measured by the terminal detector.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 145

2 Improvement on ΔE-E detector The 79Se11+ was detected with a four-anode gas ionization detector which construction and circuit were well-redesigned (Fig. 1) filled with 110 mbar P10 gas. Differential energy loss signal was measured with the anodes to give ΔE1, ΔE2, ΔE3 and ER, and shown in Fig. 2. Total energy signal was taken from the cathode. Here, a simulation of range-energy relation with ionization curve made by the software SRIM was shown in Fig. 3. As can be seen, the anode-plate length of the ionization detector quite suit for measuring this nuclide.

Fig. 1 Schematic representation of gas ionization detector

Fig. 2 Energy spectrum

a—Et；b—ΔE1；c—ΔE2；d—Er

146 Annual Report of China Institute of Atomic Energy 2007

3 Discrimination on particles 79 Two-dimensional spectra of ΔE1 and ER, gated on ΔE2, ΔE3 and ET, were used for discriminating Se from 79Br. Two-dimensional spectra for a blank sample and series standard sample are shown in Fig. 4. According to the spectra, 79Se and 79Br peaks were fully resolved owing to the high resolving power of the detector.

Fig. 3 Simulation of range-energy relation with ionization curve made by software SRIM

Fig. 4 Measured two-dimensional spectra (ΔE1-ER) of blank and series standard sample after gating on ΔE2, ΔE3 and ET a—Blank sample；b—4.60×10－8；c—4.60×10－9；d—3.01×10－10；e—4.47×10－11；f—5.22×10－12

4 Results and discussion

We discovered a kind of molecular negative ion (SeO2) which superduperly suppressed the interference from the isobar 79Br for measuring 79Se/Se ratios with AMS, and explored the chemical form of 79Se AMS samples. And then we developed chemical procedure to prepare samples for 79Se analysis by AMS. Meantime, a new ultra-sensitive method for measuring 79Se with AMS was studied. Applications of FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 147

this methodology include ultra-sensitivity quantization of 79Se in biological samples from 79Se tracer studies and environmental 79Se monitoring where sample size or analysis time is limiting would turn into feasibility. This method for measuring ultra trace 79Se in selenium isotope was validated by comparing measured 79Se/Se ratios of series standard sample which were normalized by the highest activity sample with the theoretical ratios dated from the original standard sample whose 79Se/Se ratios were calculated by the software ORIGEN (Table 1). 79Se AMS samples were counted 2 to 6 times depending on the counting precision, which was typically less than 4%. For the lower content 79Se standard sample, at least 50 counts of isotope with mass equal to 79 were detected each time. The AMS limit of detection (LOD) of the standard samples was calculated as the sum of the mean 79Se/Se ratio of 20 mg blank samples and 3 times the SD of the mean. And due to the measuring time limit and the low transmission efficiency, the LOD can only be assessed to below 1×10－12.

Table 1 Measured AMS 79Se/Se ratios and calculated 79Se/Se ratios from serially diluted standards Samples Sample size/mg 79Se/Se ratio theoretical value 79Se/Se measured value

Blank sample 20 0 0

Standard No.7 5 4.63×10－7 (4.63±0.34) ×10－7

Standard No.8 5 4.60×10－8 (4.83±0.32) ×10－8

Standard No.9 10 4.60×10－9 (4.39±0.12) ×10－9

Standard No.10 10 3.01×10－10 (3.10±0.29)×10－10

Standard No.11 10 4.47×10－11 (4.79±0.24)×10－11

Standard No.12 10 5.22×10－12 (5.08±1.69)×10－12

The 79Se/Se ratios determined by AMS were strongly correlated to theoretical ratios which were calculated from serially diluted original standard sample (Fig. 5). The linear relation was quite good (R2=0.998 94), which represents the reliability of this method. While the LOD declared that it was absolutely feasible to use 79Se as environmental and biological tracer isotope via accelerator mass spectrometry.

Fig. 5 79Se/Se ratios of serially diluted samples analyzed by AMS and theoretical ratios 148 Annual Report of China Institute of Atomic Energy 2007

High Efficiency 41Ca Measurements With AMS

WU Shao-lei, HE Ming, JIANG Shan, ZHANG Bo1, YUAN Jian, WU Shao-yong, WANG Wei, TUO Fei2, LI Chao-li3, DOU Yu-ling3, ZHANG Da-wei3, SHI Guo-zhu3 (1 College of Nuclear Science & Technology, Lanzhou University, Lanzhou 730000, China; 2 College of Physics Science and Technology, Guangxi University, Nanning 530004, China; 3 Beijing Normal University, Beijing)

41Ca is a long-lived radioisotope with a half-life of 1×105 a, it was widely used as a radiotracer in many biological experiments. For the purpose of 41Ca bio-tracing study, we developed high efficiency 41 － Ca AMS measurement using CaF2 target at CIAE HI-13 tandem accelerator. We injected CaF instead － of CaF3 . It provided a larger beam current and higher transmission in AMS system. With this improvement, we have successfully measured the many low current biological samples which we can not measure before. 41 Before the Ca samples were prepared as CaF2, there was a effective chemical separation be used. We separated Ca and K with Dowex 50 resin. After sample loading, the interfering K was eluted using 0.8 mol/L HNO3, and the Ca was eluted using 4 mol/L HNO3 solution. The CaF2 prepared was mixed with silver powder (1part CaF2:1part Ag by mass) and press into aluminum AMS sample bolders for the AMS measurement. Our ion source is cesium sputtering ion source. With this source, injected 40CaF－ beams about 60 nA intensity are routinely available. Ions were accelerated with a terminal voltage of 8.3 MV, and Ca8+ were selected after carbon foil stripping, and finally the particles were identified with a multi-anode gas ionization detectors filled 140 mbar P10 gas. Fig. 1 is a two-dimensional density spectrum of our 41Ca biological radiotracer experiments about bone calcium metabolism.

Fig. 1 Two-dimensional density spectra of E2 vs ER, the spectra were taken for a blank CaF2 sample and

biological CaF2 sample of bone calcium metabolism a—Blank sample; b—Biological sample

As we can see in the experimental spectra, the interferences were eliminated, and we can identify 41 41 Ca and K easily. Finally, we applied successive software gates on ΔE1, ΔE2, ΔE3, ΔET, ΔER to remove all interfering 41K, and then a accurate result is available. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 149

Prepare of HfF4 Samples for AMS Measurement by Solid-Phase Reaction Method

TUO Fei1, JIANG Shan, HE Ming, WU Shao-yong, BAO Yi-wen, YOU Qu-bo, HU Yue-ming, OU YANG Ying-gen, DOU Yu-ling2, HE Guo-zhu, WANG Wei, LI Chao-li2, WANG Xiang-Gao, SHEN Hong-tao, WU Shao-lei, ZHANG Da-wei2, SHI Guo-zhu2, HUANG Chun-tang2 (1 College of Nuclear Science & Technology, Lanzhou University, Lanzhou 730000, China; 2 College of Physics Science and Technology, Guangxi University, Nanning 530004, China)

182 180 － During Hf measurement by AMS, negative ion current of HfF5 is reduced if impurities with high values of electron affinities (e.g. oxygen) are present. Furthermore, if there are large mounts of 18 － 182 oxygen in samples, it is very easily to form some kinds of ions like WF4 OH , therefore, W suppression can not be achieved. In order to reduce oxygen we improved the method of preparation

HfF4 by solid-phase reaction using NH4HF2 instead of commonly used liquid-phase reaction. The principle of reaction can be expressed as formula given below:

2HfO2+5NH4HF2→2HfF4↑+5NH3↑+H2O↑+4HF↑

Fig. 1 Scheme of solid-phase reaction equipment

Scheme of solid-phase reaction setup is shown in Fig. 1. Samples prepared by solid-phase reaction were tested at AMS ion source. By measuring negative ion current F－ and O－ respectively, we can get － － the ratios of F to O . The results are listed in Table 1, together with commercially available HfF4 and samples that produced via liquid-phase reaction. From the results we can see, F－ /O － ratio of solid-phase reaction samples is 2-3 times of that liquid-phase reaction and commercially available HfF4. 180 － Also, negative ion current of HfF5 can reach up to 150 nA (for naturally abundance samples), it is 2 times larger than that of liquid-phase reaction.

－ － Table 1 Comparison of F /O ratio in three kind of HfF4 samples F－/O－ ratio Material Experiment 1 Experiment 2 Experiment 3 Experiment 4

HfF4 perpared by liquid-phase reaction 6.2 5.4 5.7 9.5

Commercially available HfF4 5.2 7.5 7.8 6.5

HfF4 prepared by solid-phase reaction 19.1 14.0 10.6 30.5

150 Annual Report of China Institute of Atomic Energy 2007

Improvement of AMS Measurement of 182Hf

TUO Fei1, JIANG Shan, HE Ming, WU Shao-yong, BAO Yi-wen, YOU Qu-bo, HU Yue-ming, OU YANG Ying-gen, DOU Yu-ling2, HE Guo-zhu, WANG Wei, LI Chao-li2, WANG Xiang-Gao, SHEN Hong-tao, WU Shao-lei, ZHANG Da-wei2, SHI Guo-zhu2, HUANG Chun-tang2 (1 College of Nuclear Science & Technology, Lanzhou University, Lanzhou 730000, China; 2 College of Physics Science and Technology, Guangxi University, Nanning 530004, China)

The detection limit for 182Hf at CIAE HI-13 AMS systems still could not satisfy various applications (e.g. detection of a nearby supernovae signal). Therefore, techniques were developed in this work to improve the AMS measurement of 182Hf after a new injector was built. Mass resolution of the injector can reach 630 by scanning of HfF4 sample when the object point and image point slit is set at ±2.5 mm and ±1 mm, respectively. In this condition, losing 5% of beam current comparing with the beam current of slits is completely opened up. In order to enhance the transmission efficiency from low-energy side Faraday-cup to detector, we 180 － use pre-accelerate energy of 112 kV and terminal voltage of 8.5 MV. Also, we extracted HfO2 182 9+ 180 － directly to simulate Hf by using HfO2 samples instead of that extracted HfF5 from HfF4. Thus, 182 9+ 180 － the simulation of Hf becomes more easily and more convenient, because HfO2 current is much 180 － larger than HfF5 and have higher transmission efficiency. By scanning of electrostatic analyzer (ESA), we got the best voltage of ESA for measurement of 182Hf. At present, we are currently got some primary results for 182Hf/180Hf isotope ratios at 6×10－10 with transmission efficiency of 1.01×10－4. By using the Time of Flight (TOF) detector setup combined with a effectively chemical separation, a measurement of 182Hf/180Hf ratio at 10－12 level may soon be possible.

Study on Reflection of Infrared Light Through Polyester Films Modified by Nuclear Pores

LIU Cun-xiong, NI Bang-fa, HU Lian, TIAN Wei-zhi, WANG Ping-sheng, XIAO Cai-jin, ZHANG Gui-ying, LV Peng, HUANG Dong-hui

Polyester membranes with thicknesses of 20 and 50 μm were bombarded by 32S ions from the HI-13 tandem accelerator of China Institute of Atomic Energy to produce latent tracks. Using different chemical etching conditions and sensitization, latent tracks became cone-shaped and cylindrical pores with diameters of 1 and 3 μm. Reflectivity was measured for infrared light (wavelength 2-10 μm). The results indicate that with solid state nuclear track modification, the reflectivity of tested polymer materials can be as low as 5% for 3.3-10 μm wavelength. The irradiated polyester samples were treated with Process 1 and Process 2. 1) Process 1 Dipped into sodium hydroxide solution (concentration, 6.25 mol/L; temperature, 65 ℃ ) for 10 min, immersed in dimethyl formamide for 10 min at a temperature of 60 ℃, dipped into sodium hydroxide solution(concentration, 6.25 mol/L, temperature, 65 ℃ ) for different time. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 151

2) Process 2 Dipped into sodium hydroxide solution (concentration, 6.25 mol/L; temperature, 65 ℃ )for 2 min, irradiated for 2 h by a ultraviolet light of 350 nm wavelength, immersed in diethyl formamide for 10 min at temperature of 60 ℃, dipped into sodium hydroxide solution(concentration, 6.25 mol/L; temperature, 65 ℃ ) for different time. After process 1cylindrical pores of 1 μm diameter were produced (Fig. 1), and the loss of surface is weak. Conical pores of 3 μm diameter were gotten using PEW solution (NaOH:C2H5OH:H2O=1:3:5)at temperature of 65 ℃ (Fig. 2).

Fig. 1 Cylindrical pores of 1 μm diameter Fig. 2 Conical pores of 3 μm diameter

Fig. 3 Reflectivity of untreated samples

Fig. 4 Reflectivity of treated samples

152 Annual Report of China Institute of Atomic Energy 2007

Polyester membranes with thickness of 20 μm(irradiation density 109 cm－2) were treated with Process 1. The sodium hydroxide solution etching time is 10 and 12 min, respectively. Fig. 3 shows the relative reflectivity of untreated samples. The reflectivity is about 47% for 1.3-10 μm. After samples were etched 12 min, the reflectivity decreases to 14% for 1.3-5.0 μm, and 5％ for 5.0-10.0 μm. Polyester samples were treated with Process 2, etched 15, 18 and 20 min respectively. When the etching time is 20 min the reflectivity reduces to 14% for 1.3-3.3 μm, 5% for 3.3-10.0 μm (Fig. 4).

Preliminary Study on a New Generation Natural Matrix Reference Material Suitable for Microanalysis*

HUANG Dong-hui, NI Bang-fa, TIAN Wei-zhi, WANG Pings-heng, LIU Cun-xiong, ZHANG Gui-ying, XIAO Cai-jing, HU Lian, LV Peng

This work is preliminary part of a research project aiming at producing a new generation natural matrix reference material (RM) by using a combination of several available nuclear analysis techniques to satisfy the demand of quality control in microanalysis.

1 Preparation of material Ten kg each of two kinds of stream sediment reference materials were selected and mixed. The mixture is presumed to be more suitable for instrumental neutron activation analysis. Through desiccation, sterilization, pulverization and homogenization, the maximal particle diameter of the final material is 13 μm, and the most probability particle diameter is 3 μm. The particle diameter distribution is shown in Fig. 1.

Fig. 1 Particle diameter distribution

2 Homogeneity test Sampling behavior of multielements in the prepared material was studied under different sample size levels by using several available nuclear analytical techniques (NAA-PIXE-SRXRF). 2.1 NAA test Fifty each of two sets of subsamples were prepared with sample sizes of 5 and 1 mg, respectively, for INAA. In each set, two subsamples were taken from each of 25 bottles. About 30 elements were determined in each subsample with analytical uncertainties better than 3%. The results manifested that the FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 153

number of elements with sampling uncertainties better than 1% is 19 for 5 mg sample size, and 17 for 1 mg sample size. The sampling uncertainties of most other elements determined are between 2%-5% under both sample size levels. 2.2 PIXE test One subsample from each of 20 different bottles was taken for homogeneity test by PIXE. This work was performed at the PIXE system of Beijing normal university (beam diameter is 3 mm, proton energy is 3 MeV). Three beam spots of each subsample were measured by PIXE. The number of elements determined by PIXE is 15, among which, the sampling uncertainties of 9 elements are better than 1%, and those of the other 6 elements are better 3%. According to proton energy and individual X-ray ranges, it is estimated that the effective sampling sizes for all the measured elements are less than 1 mg. 2.3 SR-XRF test SR-XRF homogeneity test was performed at the KEK state lab of Japan. The beam dimension is 5 μm×5.5 μm, beam current is 360 mA and the energy of excitation X-rays is 17.5 keV. One subsample was taken from each of 16 different bottles, 6 beam spots of each subsample were measured. It is estimated that the effective sample sizes are between several ng to several tens ng for different elements determined, according to the ranges and absorption coefficients of characteristic X-rays. The total number of elements determined by SR-XRF is about 20, 15 of which with counting statistics better than 3%. The results showed that at least 3 elements in this material have sampling uncertainties better than 10% at ng sample size level.

* Supported by National Natural Science Foundation of China (10575138)

Preliminary Study on Sampling Behavior of Multielements in NIST RM 2703 and SRM 2702 by Using Neutron Activation Analysis 

HUANG Dong-hui, TIAN Wei-zhi, NI Bang-fa, WANG Ping-sheng, ZHANG Gui-ying, LIU Cun-xiong, XIAO Cai-jing, LV Peng , HU Lian

1 Experimental 1.1 Sample preparation and irradiation Sub-samples of NIST RM 2703 and SRM 2702 (marine sediment reference materials) of 0.8-1.4 mg each were accurately weighed using microbalance and wrapped with PE bags (for short irradiations) and Al foil (for long irradiation), respectively. One sample each of about 25 mg RM 2703 and SRM 2702 was prepared for pre-verification of homogeneity of Na and Mn by post-irradiation sampling. Chemical standards for elements determined were prepared using high purity metals and oxides/nitrates. CRMs GBW 07311, 07312 (stream sediment) and NIST SRM 1632a (coal powder) were used for analytical quality control. 1.2 Data acquisition and analysis A HPGe gamma-ray spectrometer(Canberra, 35%, 1.8 keV) was used for counting. Computer software SPAN and ADVNAA were used for peak analysis and elemental quantification, respectively.

2 Results and discussion

2.1 Basic principle of Ks determination by INAA

For the analysis of any “random subsamples” in solid material, a total uncertainty Ut attached to an 154 Annual Report of China Institute of Atomic Energy 2007

analytical result is a quadratic sum of analytical uncertainty Ua and sampling uncertainty Us, as expressed by: 2 2 2 Ut =Ua ＋Us (1)

Where Ut can be estimated by the relative standard deviation (in percentage) over a group of subsamples, Ua is the relative statistic uncertainty in analysis (in percentage). Relative sampling uncertainty is practically estimable when the analytical uncertainty is sufficiently small (compared with the total uncertainty, or standard deviation) and accurately known.

According to the ingamells model, the sampling constant Ks for a certain element in a well-mixed material is defined as the minimum sample needed to limit the relative sampling uncertainty to 1% at a 68% level of confidence in a single determination, as expressed in the following equation: 2 Ks = R w (2) 2 2 Where R is the relative sampling uncertainty (R and Us of Eq.(1)) in percentage, determined from the analysis of a group of sub-samples with the mass w each. Rewriting Eq.(1) as: 2 2 2 R =Ut －Ua (3) INAA is an effective analytical method to study the sampling behavior of individual elements in natural matrix CRMs/RMs with weighable sample sizes, for its unique features of non-destruction, multielemental ability, and small and well quantified analytical uncertainties in many cases.

2.2 Ks constants of Na and Mn determined by using post-irradiation sampling For the natural matrix samples SRM2702 and RM2703, under 1mg sample size level, the sampling uncertainties of Na and Mn were determined to be less than 1% by using sampling after irradiation. The pre-verification of satisfied homogeneity of Na and Mn by post-irradiation sampling solves the problem associated with possible sample weight losses in the procedure of sampling before irradiation and transferring after irradiation in the study on sampling behavior of multielements at this sample size level.

2.3 Multielements Ks determination and comparison in RM 2703 and SRM 2702

To assure the reliability and practicability of Ks constants, only the elements with analytical 2 2 1/2 uncertainties less than 4% were studied in this work. Sampling uncertainty Us(R)=(RSD －Ua ) . 2 Ingamells’s sampling constant Ks＝R w. When the analytical uncertainty is larger than standard deviation, 2 Ks is conservatively estimated by Ua w. RM 2703 and SRM 2702 are of the same matrix with different particle size distributions. At 0.8-1.4 sampling size level, 12 elements of Al, As, Ce, Fe, La, Mn, Na, Sc, Ta, Th, V, and Zn were proved to be homogeneous enough with sampling uncertainties all within 1% (as shown in Table 1). Under this sample size level, the concentration values of elements having satisfied homogeneity should be the same as the certified values of corresponding elements under conventional sampling size level (usually 100 mg or larger). Comparing with SRM 2702 (the most probability particle diameter is 5 μm, the maximal particle diameter is about 100 μm ), the finer particle distributed RM 2703 (the most probability particle diameter is 3 μm, the maximal particle diameter is about 10 μm ) exhibits better homogeneity, as obviously manifested by the Ks constants being 200, 150, 100 and 30 mg, respectively for 4 elements: Dy, Hf, Lu and Sb, for RM2702; and <4, <16, 7.5 and 1.2 mg, respectively, for SRM 2703 (as shown in Table 2). This work verified that INAA could be used to identify elements in (certified) reference materials with satisfied homogeneity at sample sizes down to 1 mg level, so that a new generation CRMs certified with element-specific and down to 1 mg sample size levels may be established. Combining with nuclear micro-beam analyses, it is hopeful to extend the minimal sampling sizes down to ng level.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 155

Table 1 Multielements sampling behavior of NIST RM 2703 and 2702

Element Sample RSD/% Ua/% R/% Element Sample RSD/% Ua/% R/%

Al SRM2702 3.0 2.9 1.0 Mn SRM2702 1.1 1.0 0.6

RM2703 2.2 2.8 1.8 RM2703 0.9 1.0 0.9

As SRM2702 2.2 2.1 0.6 Sc SRM2702 2.0 1.8 ＜1

RM2703 2.2 2.1 0.7 RM2703 1.0 1.8 1.0

Ce SRM2702 2.2 2.2 0.4 Ta SRM2702 2.9 2.8 0.9

RM2703 2.4 2.2 0.8 RM2703 2.2 2.8 0.9

Fe SRM2702 1.8 1.5 0.9 Th SRM2702 2.8 2.7 0.9

RM2703 2.0 1.8 0.8 RM2703 2.3 2.7 1.0

La SRM2702 2.1 1.8 ＜1 V SRM2702 2.7 2.5 ＜1

RM2703 1.1 1.8 0.9 RM2703 2.7 2.5 0.8

Na SRM2702 1.3 0.9 1 Zn SRM2702 2.6 2.4 ＜1

RM2703 1.1 0.9 0.5 RM2703 2.6 2.4 0.9

Table 2 Comparison of 4 elements sampling behavior between NIST RM 2703 and 2702

2 Element Sample RSD/% Ua/% R/% R w Ks/mg

Dy SRM2702 14.3 4 13.7 188.2 200

RM2703 2.9 4 ＜4 ＜16 ＜16

Hf SRM2702 12.4 2.1 12.22 149.4 150

RM2703 2.0 2 ＜2 ＜4 ＜4

Lu SRM2702 11.3 3.2 10.8 117.5 120

RM2703 4.21 3.2 2.7 7.5 7.5

Sb SRM2702 5.5 1.8 5.15 26.6 30

RM2703 2.4 1.8 1.1 1.2 1.2

Performance Improvement on CIAE Neutron Dosimetry Bubble Detectors

ZHANG Gui-ying, LV Peng, NI Bang-fa, TIAN Wei-zhi, WANG Ping-sheng, WANG Zhi-qiang, LUO Hai-long, HUANG Dong-hui, LIU Cun-xiong, XIAO Cai-jin, HU Lian

Three aspects in the design of our neutron dosimeter bubble detectors developed in 2007 have been renovated. They are: 1) The use of composite superheated liquid in place of single compound one; 2) Redesign of the container for bubble detectors; 3) Redesign of the recompression head for bubble detectors. These renovations have brought an important upgrade in overall performances of our bobble detectors.

1 Experiment In the irradiation experiment, a neutron dose rate-calibrated 241Am-Be neutrons source from the Department of Radioactive Metrology, CIAE, was used. Four detectors were parallelly placed (Fig. 1) in the center of a normal phantom (material: organic glass; size: 30 cm×30 cm×15 cm，the plane of 30 cm× 30 cm is upright to the axis of the beam) 2 m away from the target to ensure the same dose can be received 156 Annual Report of China Institute of Atomic Energy 2007

by the four detectors. After irradiation, the number of bubbles formed was read by naked-eyes. All the detectors tested were successively irradiated in pairs as mentioned above. The dose received by each batch of detectors is given in Table 1. The detection sensitivity is defined as the number of bubbles divided by the dose received

Fig. 1 Phantom

2 Results and discussion 2.1 Dose response The functions of bobble number vs dose are shown in Fig. 2, 3. Fig. 2 is for the newly designed detectors with a range of dose being 5 to 40 μSv. Fig. 3 is for the original 2007 products. The dose response function is y=1.581x (y and x stand for bubble number and dose in μSv, respectively) for the new detectors with a correlation coefficient of 0.992 7, compared to 0.275 9 for the old ones. The test results indicate the detection uncertainty can be largely reduced by the improvement of bubble detector.

Fig. 2 Neutron dose vs number of bubbles for post-improvement bubble detector

2.2 Reproducibility tes Table 1 shows the results of five detectors irradiated under 10 μSv dose in each run, and repeated for 4 runs. For each of the dosimeters, the mean value of the readings, m , standard deviation S and the half －1/2 widths of standard deviation IS were calculated, IS=tS(2n－4) , with t being the student’s value and n [1] the number of measurements. According to ISO, the value of 100(S+IS)/ m should be smaller than 25. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 157

From Table 1, we can find all of the detectors measured meet the ISO standard. The detectors improved can be used repeatedly.

Fig. 3 Neutron dose vs number of bubbles for pre-improvement bubble detector

Table 1 Results of reproducibility test

Sample Source n m S IS 100(S+IS)/ m

1 241Am-Be 4 19 2.309 1.03 17.57

11 241Am-Be 4 18.75 1.708 0.76 13.17

13 241Am-Be 4 18 1.633 0.73 13.11

15 241Am-Be 4 16.5 1.732 0.77 15.17

A2 241Am-Be 4 18.5 0.577 0.26 4.51

Reference: [1] VANHANVERE F, ERRICO F D. Standardisation of superheated drop and bubble detectors. Radiation Protection Dosimetry, 2002, 101: 283-287.

Study on Stability of Personal Neuron Dosimetry-Bubble Detectors

ZHANG Gui-ying, LU Peng, NI Bang-fa, TIAN Wei-zhi, WANG Ping-sheng, LIU Cun-xiong, HUANG Dong-hui, XIAO Cai-jin, HU Lian

The stability is one of the most important parameters of neutron bubble detectors for monitoring personal neutron dose. This report presents a preliminary analysis on stability of a home-made personal neuron dosimeter-bubble detector after the prescription and technique have been improved. A detector was irradiated by 252Cf neutron sources for 10 min at the third position as shown in Fig. 1. After irradiation, the bubble numbers formed was read out by naked-eyes. The bubbles were then recompressed back into liquid drops and stored about 23 h at the temperature of 25.5 ℃ for the next test. The results in Fig. 2 prove the stability of the detector used for monitoring doses of 252Cf neutron sources. 158 Annual Report of China Institute of Atomic Energy 2007

It shows there are 23.3 bubbles produced after irradiated for 10 min at the third position by the 252Cf neutron.

Fig. 1 Irradiation positions of 252Cf neutron source

Fig. 2 Results of stability test

Development of α Grid Ionization Chamber

YANG Lu

The study concerns in the development of parallel plate grid ionization chamber which used to measure the α radioactivity. The developed facility can analyze the sample of the environment, material and the biology. It is also used for nuclear explosion，the nucleus analyze of the simulated nuclear explosion，the nucleus analyze of the depleted uranium，extensive fuel disposal and the measurement of the total α activity. The facility is composed of main body chamber，gas-filled and electronics systems. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Physics 159

The stainless steel crust of the chamber is cylinder, the inner diameter is 238 mm，the high is 314 mm，the thick of the wall is 3.3 mm，the volume is 14 L. The working gas is 90%Ar（purity of 99.9%）+10%CH4 （purity of 99.9%） mixture gas. The gas flow rate is 50 mL/min. From fetching out the anode and the grid signals，grid ionization chamber can measure the energy and the angular distributions for charged particle，the detection efficiency is 100% for charged particle， solid angle approaches to 2π.

Photoelectric Detector of GaAs Compound Semiconductor

DING Hong-lin, HAO Xiao-yong, MENG Xin, ZHANG Wan-chang, ZHANG Kai

The photoelectric detector of GaAs compound semiconductor can be used to detect the pulse radiation beam. The photoelectric detector of GaAs and InP compound semiconductor was coupled with a constant voltage. The resistance of photoelectric detector is declined, but the output electrode can transport a current pulse signal which is proportional to resistance changes in the case of X- and γ-ray pulse beam radiation. In this researched study the surface barrier technology was used to prepare the photoelectric detector of GaAs compound semiconductor. The preparation process is following. 1) Cutting Select the high resistance GaAs crystal (ρ≈108 Ω·cm) from LEC technological growth and a rectangle strip sample with the length of 5-6 mm and the width of 16 mm was cut. The two ends of the ground was ground into 45 degree angle and a appropriate thickness less than or equal to 300 μm. 2) Surface treatment

The cleaned sample was corroded in the etched solution (V(H2SO4): V(H2O2): V(H2O)=3:1:1) at 50 ℃ for 2-3 min. The etched sample was cleaned with the deionizer water. 3) Evaporation of electrodes The rectangular samples of two end points NiGeAu were treated at 360-430 ℃ for 10-15 min. 4) Detector encapsulation Some testing results of the photoelectric detector of GaAs compound semiconductor is shown in Fig. 1.

a b Fig. 1 Some testing results a—Rise time is 104.9 ps, decrease time is 897.7 ps, the distinguishable time is 1.369 ns;

b—Rise time is 176.0 ps,decrease time is 1.636 ns, the distinguishable time is 489.3 ps 160 Annual Report of China Institute of Atomic Energy 2007

Development of Large Area CdZnTe Detector for Satellite Detection of X- and γ-ray

DING Hong-lin, MENG Xin, HAO Xiao-yong, ZHANG Kai

Cadmium-Zinc-Tellurium (CZT) detectors achieve excellent spatial and energy resolutions in the broad energy range from 30 keV to 600 keV without cooling. Thus, CTZ detectors become a major detector used to research the field of X- and γ-ray in space and astronomy. The present research concerns in the modified structure of discriminator grade planar CZT detector with the side of 10 mm×10 mm×5 mm and the development of large area detector composed of four individual 10 mm×10 mm×5 mm Frisch-grid CZT detectors. Good linear energy response to 125I, 241Am, 57Co, 133Ba, 137Cs γ-ray and good energy resolution for 137Cs γ-ray have been achieved for the developed large area detector. The experiment results are showed Fig. 1.

Fig. 1 Energy spectra using modified 10 mm×10 mm×5 mm Frisch-grid CZT detector a—125I; b—241Am; c—57Co; d—137Cs

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·High Power Laser and Accelerator 161

High Power Laser and Accelerator

Laser Induced Damage Threshold of Dielectric Coatings for Improving of Heaven-I System

GAO Zhi-xing, TANG Xiu-zhang, QI Hong-ji1 (1 Shanghai Institute of Optics and Fine Mechanics)

To improve the laser induced damage threshold of optics in heaven-I system，some multilayer coatings deposited by e-beam reactive evaporation technique onto fused silica substrates using the materials of hafnium dioxide, aluminum oxide and silicon dioxide aluminum were studied. To study the laser induced damage of optics, a KrF laser induced fluorescence image system was built. The results indicates that the absorption of defects greatly contribute to laser induced damage threshold of thin films. The control of defects, especially defects with strong absorption, is still the only way to improve the laser radiation resistively of coatings in the UV spectral region. By controlling defects and the electric field distribution of thin film, the KrF laser induced damage threshold of multilayer high-reflectance film was improved to 5 J/cm2.

Preliminary Study of Single-Shot SHG-FROG Measurement of Femtosecond Laser Pulses

XU Yong-sheng, ZHANG Xiao-hua

We combine the single shot SHG autocorrelator and the spectrometer in our laboratory to set up a single shot SHG-FROG measurement apparatus. FROG is the initial abbreviation of frequency-resolved optical gating, which basic principle is described as follows: the laser to be measured is splitted into two beams at first, one of which is used to be probe beam, and another be switch beam, then the two beams are combined in the nonlinear medium to interact to each other to produce the double frequency laser, and then the new laser is coupled into the spectrometer to be resolved in frequency domain, and at last, a 2D CCD array is used to capture the spectrogram from the spectrometer. In the base of the data obtained by the CCD, using the method of FFT iterative, we retrieve the electric field distribution, phase, and the corresponding chirp information from the spectrogram in the time and frequency domains. The calibration of CCD wavelength axes is 0.035 nm/pixel. The calibration of CCD time axes is 18.4 fs/pixel. The FROG spectrogram obtained in the experiment is shown in Fig. 1. According to the calibration results, the central wavelength is 377.208 nm. We input the parameters obtained from the calibration into the FROG retrieve program, and after several iterative operations, we obtained the information about the electric field and the corresponding phase in time and frequency domains, the bandwidth and the pulse duration, etc. Figure 2 is the retrieved FROG image. The FROG image has a lot of smearing, which is caused probably by the image error of the focusing mirror. 162 Annual Report of China Institute of Atomic Energy 2007

Figure 3 and 4 are the retrieved temporal intensity and corresponding phase distribution, spectrum intensity and corresponding phase distribution. In time domain, the phase varies linearly, which indicates that the pulse has almost no chirp. In frequency domain, the phase is almost constant, which indicates also that the pulse has no much chirp. The retrieved laser parameters are: the FROG error is 5.082×10－3, the pulse duration is 110.2 fs, the bandwidth is 4.932 nm, the time-bandwidth product is 0.286 7. Compared with the time-bandwidth of the asymmetrical hyperbolic secant laser in the Fourier transform limit, 0.278, we can find that the pulse laser shape from TSA is approximately asymmetrical hyperbolic secant, and the TSA output pulse laser central wavelength is 754.135 nm. From the experiment and theoretical analyses above, we can conclude that it is feasible to measure the parameters of the chirp pulse amplification system TSA using the single shot SHG-FROG.

Fig. 1 Measured FROG image Fig. 2 Retrieved FROG image

Fig. 3 Retrieved electric field and phase Fig. 4 Retrieved spectrum field and phase

Experimental Study of Interaction for Ultra-short Pulse Laser With Solid Plasmas

LI Ye-jun, LU Jian-xin, WANG Lei-jian, HUANG Yong-sheng, ZHANG Ji, ZHANG Hai-feng, TANG Xiu-zhang

Hot electron spectrum and angular distribution generated from the interaction of ultra-short pulse laser (744 nm/120 fs/12 mJ) with solid (Cu) plasma target have been studied experimentally which have FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·High Power Laser and Accelerator 163

been measured utilizing electron-magnetic meter and imaging plate (IP). And the angular distribution was measured in the incidence plan. At the condition of pre-pulse free and P polarization and 45º incidence, the temperature of hot electron fitted by Maxwellian is 56 keV, and the hot electrons are emitted mainly along the normal of targets. The dominant mechanism of hot electron generation is vacuum heating. The charge separation potential is about 70 keV. Figure 1 shows the hot electron spectrum measured in the target normal direction generated by infrared laser with copper target. And the Fig. 2 gives the hot electron angular distribution in front of target, and zero degree is the target normal direction.

Fig. 1 Spectrum of hot electron measured in target normal direction

Fig. 2 Hot electron angular distribution in front of target

Experimental Study of Effect for Hot Electron Producing With Various Laser Wavelength

LI Ye-jun, WANG Lei-jian, HUANG Yong-sheng, LU Jian-xin, ZHANG Ji, ZHANG Hai-feng, TANG Xiu-zhang

Two kinds of wavelength ultra-short pulse (744 nm/120 fs/12 mJ, 248 nm/630 fs/35 mJ) laser have been used to study interaction with solid (Cu) plasmas targets. The hot spectra and angular distribution 164 Annual Report of China Institute of Atomic Energy 2007

have been measured utilizing electron magnetic spectrometer and imaging plate (IP) detectors in laser incidence plan. At pre-pulse free and P polarization and 45º incidence, the temperatures of hot electron fitted by maxwellian is 56 keV and 22 keV, respectively, and the hot electrons are emitted mainly along the normal of targets in two conditions. The dominant mechanisms of hot electron generation are vacuum 1/2.1 heating (VH). For the first time we validate that scaling law of VH is Th≈(Iλ2) keV at home. The charge separation potential are about 70 keV and 45 keV, respectively. Fig. 1 is showed the hot electron spectrum measured at the target normal direction generated by infrared laser with copper target. Fig. 2 shows the hot electron spectrum produced by ultraviolet laser with copper target. And the Fig. 3 gives the hot electron angular distribution in front of target, and zero degree is the target normal direction.

Fig. 1 Spectrum of hot electron generated Fig. 2 Spectrum of hot electron generated by infrared laser measured in target normal direction by ultraviolet laser measured in target normal direction

Fig. 3 Hot electron angular distribution in front of target

Experimental Results of Target Velocities Detected by Side-On Shadowgraph System

GAO Shuang, TANG Xiu-zhang, WANG Zhao, LIANG Jing, LU Jian-xin

Experimental measurements of EOS have more and more attention from many physical fields, such as physical geography, astrophysics, ICF, science of material, physics of nuclear weapons. They are FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·High Power Laser and Accelerator 165

important to the practical application and the development of theory of EOS. A series of researches in EOS done by ultraviolet long pulse laser “Heaven-Ⅰ”, had prominent characteristics and developed very well. As an important technique to detect the target in EOS, side-on shadowgraph had been wildly applied all the while. Based on the specific condition and the practical request of the lab, with the help of argon ion laser and internal focusing telescopes, the side-on shadowgraph system had been set up to test the speed of flyers. The 50 μm thick aluminum target was imaged on the slit of streak camera through the lens which focal length was 37 cm. Six beams of laser were used in the experiment. The intensity was 8.3×1011 W/ cm2. The total energy was 66 J. The beams had a 28 ns temporally Gauss profile. The result of the experiment was showed in Fig. 1. The experimental data was showed in Fig. 2.

Fig. 1 Result of 50 μm Al experiment Fig. 2 Experimental data of 50 μm Al experiment

The interval between the time when the laser reached the target and the time when the target started to fly is 19 ns. The linear fit was done between the data from 19 ns to 64 ns. The slope which also revealed the target velocity was 2.76 km/s. The 13 μm thick aluminum target with 100 μm ablator was imaged on the slit of streak camera through the lens which focal length was 37 cm. Six beams of laser were used in the experiment. The intensity was 7.2×1011 W/cm2. The total energy was 68 J. The beams had a 33 ns temporally Gauss profile. The result of the experiment was showed in Fig. 3, and the experi- mental data was showed in Fig. 4. The interval between the time when the laser reached the target and the time when the target started to fly is 29 ns. The linear fit was done with the data from 29 ns to 58 ns. The slope which also revealed the target velocity was 3.34 km/s.

Fig. 3 Result of 13 μm Al Fig. 4 Experimental data of 13 μm Al

166 Annual Report of China Institute of Atomic Energy 2007

A side-on shadowgraph system was developed for the velocity of the target in the equation of stats experiments, by use of the visible laser as probe. Several experimental results were gotten. It was the first domestic application of this method. In order to detect the target velocities more accurately and effectively by use of the side-on shadowgraph system, the power of the probe laser must be increased.

Titanium Film Protection and Uniformity of Beam

LI Jin-hai

The electron beam of the 10 MeV radiation electron accelerator must pass through a thin titanium film. Because the titanium film not only insulate the vacuum but also be transparent for the electron, it must be thin. However, the power of the beam is high up to 15 kW, and the beam spot whose diameter is only 11 mm is small. The normal statue of the beam should be scanned by a magnetic scanner, which reduces the power of the unit area. If the beam bombards one point for a long time, the titanium film will be perforated quickly, and then the vacuum of the accelerator tube is destroyed and the electron gun is poisoned. In order to protect the titanium film, we designed two sets of scheme, the first is to use one lens and one magnetic scanner, the other is to use two magnetic quadrupole. There are two accelerator elements being used in each of the two sets of scheme, which can be sure that any one of the element failed to work can not induce the titanium film perforation, and it is impossible that the two elements failed to work at the same time. In the most case, the distribution of the beam in the transverse plane should be according to the Gauss function, that is, the particle density of the beam center is high and that of the beam edge is low. So another element for the beam uniformity is needed. And we design a nonlinear magnetic for the beam uniformity.

Design of Radiation Shield for 2 MeV Accelerator

LI Jin-hai, ZHANG Li-feng, MA Yan-yun

The high energy electron beam is used in the industry and society more and more. Because it produces lots of X rays when it interact with material and the X rays can damage the human body, the beam must be shielded. In order to save the material and the cost, and to reduce the weight of the shield, the shield must be optimized. First, we calculate the radiation dose of the different material along the beam direction by the Monte-Carlo code. Second, we compare the result with the experience function and obtain the needed thickness of the shield. Third, according to the calculation result, we obtain the shield thickness in the different direction. The purpose of the optimization is that the shield thickness of any direction form the radiation source should not less than the calculation result, and then, we can obtain a profile curve of the shield. In order to simplify the manufacture, we use several plane to near toward the curve and obtain the reasonable mechanical parameters of the shield.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·High Power Laser and Accelerator 167

Performance of Beijing Pulsed Variable-Energy Positron Beam

MA Yan-yun, WANG Bao-yi1, YU Run-sheng1 (1 Institute of High Energy Physics, Chinese Academy of Sciences，Beijing 100049, China)

In order to study the depth-dependent characteristics of open-volume a defect near the surface of materials, the pulsed variable-energy positron beam has been constructed which consists of a pulsing system, an electronic system and a detector. The continuous beam is transformed into a pulsed beam by the pulsing system, which consists of a reflection type chopper, a prebuncher and a buncher. The buncher is a quarter-wave coaxial resonator and the RF signal is fed in by a coupling loop. The resonance frequency of the buncher is 149.89 MHz and the reflection factor is about 0.05 measured by network analyzer. The Q-factor of the buncher is about 2 000. The stop signal for the positron lifetime measurement and the power signal for the pulsing system running are supplied by the electronic system.

The signal for the positron annihilation is detected by a BaF2 scintillation detector using as the start signal of the positron lifetime measurement. The scintillator is attached to a Hamamatsu R3377 photomultiplier (PMT) with silicone oil. As the detector is inside the magnetic field generated by Helmholz coils, it is placed into a magnetically shielded detector well. In order to define the resolution function of the system, some standard samples have been measured. The resolution of the system is 295 ps.

Work Statement for Accelerating Tube With High Capture Efficiency

MA Yan-yun, ZHU Zhi-bin, ZENG Zi-qiang

The accelerating tube is the core of a linac. A constant gradient accelerating structure is chosen to accelerate the electron beam, and the designed phase velocity is linearly increased along the tube. By adjusting the size of the accelerating cavity and the phase velocity function, 90% capture efficiency is reached. The checking calculation has been finished and the optimization for the end face of bore has been done. The coupler has also been designed. Now the model cavities are being machining. In order to research the influence caused by the length of probe, the radius of the hole and the pressure, some measurements have been done. According to the experiment results and the HFSS simulation results, the length of the probe is 1 mm and the radius of the hole is equal to the radius of the standard N connector. We have designed a device for the field distribution measurements based on the perturbation method. A constant resistance accelerating structure has been designed as a technical storage.

168 Annual Report of China Institute of Atomic Energy 2007

Science and Technology of Reactor

Calculation Research for Bubble Effect Experiment of Uranium Solution

LIU Hong-wei, XIA Zhao-dong, ZHU Qing-fu

The bubble effect is very important to evaluate nuclear critical accident in nuclear solution system. We have carried out calculation research for the bubble effect of uranium solution in 2007. For the bubble effect experimental scheme, we used a semi-empirical model for the spherical bubble growth to analyze the force balance acting on the bubble and predict the bubble diameter and its final speed. Using this result, we set up the mathematical model. Then, we calculated the bubble effect of uranium solution. It established the basis for constructing the method of evaluating nuclear critical accident in nuclear solution system.

Assessment of Critical Flow Model in RELAP5

CHEN Yu-zhou, YANG Chun-sheng

An assessment of the critical flow model in RELAP5/MOD3.2 was made by comparison of the code predictions with the data obtained at super Moby-Dick facility under steady-state condition with nozzle of D=15.48 mm and L=150 mm, at ROSA-IV/LSTF SB-LOCA test with orifice of D=22.5 mm, and at Marviken large scale facility with shorter nozzles of D=200-509 mm and L/D of 0.33-3.72. In the code calculations the thermal non-equilibrium /equilibrium options and choking/non-choking options were tested. In addition, some sensitivity calculations for the nodalization of nozzle were made. The calculations are as followings. 1) The option of thermal equilibrium/non-equilibrium has great effect on the prediction for lower subcooling and lower quality region, while it has less effect for higher subcooling or higher quality region. 2) For orifice break, at subcooled condition non-choking model gives more reasonable prediction of discharge flow rate than choking model. 3) The nodalization for simulation of the nozzle has appreciable effect on the prediction results. The result suggests the importance of use’s factor, and the proper option is relative to the upstream pressure, quality and the break geometry.

Function Qualification Tests of Specified Pressure Difference Check Valve

ZHANG Xue-feng, QI Xiao-guang, DING Zhen-xin, CHEN Zhong-min, WANG Wei

Specified pressure difference check valve 20CH1H61Y-420P is a check valve with high temperature and high pressure, which holds upper design test parameters and can be used to the nuclear power plants. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Science and Technology of Reactor 169

It is a nuclear class valve, so we must validate its validity through the tests of function qualification before use it.

1 Mostly design parameters Design pressure, 25 MPa; Operation pressure, 20 MPa; Design temperature, 300 ℃ ; Operation temperature, 280 ℃ ; Unseal pressure difference, (1.4±0.1) MPa; Design diameter, 20 mm; Seal pressure difference, 1.2 MPa.

2 Tests content 1) Cold cyclic test: Test medium temperature is at room temperature not exceeding 38 ℃ . The system pressure is 20 MPa. The test medium is class water. Unseal pressure difference, (1.4±0.1) MPa; Seal pressure difference, 1.2 MPa. The basis for qualification is the 2 000 times to open and close the valve, and checking the leak of the valve seat every 500 times. 2) Hot cyclic test: Test medium temperature is 350 ℃ . The system pressure is 20 MPa. The test medium is class water. Unseal pressure difference, (1.4±0.1) MPa; Seal pressure difference, 1.2 MPa. The basis for qualification is the 2 000 times to open and close the valve, and checking the leak of the valve seat every 500 times. 3) Cold and hot exchange test: The Tests loop raises the temperature from the room temperature to 350 ℃ and the pressure from 1atm to 20 MPa. Falling down the temperature, the pressure back to the room temperature and 0.1 MPa by the speed of 50 ℃ /h. Checking the valve seat, the surface of valve cover and the leak of valve. Experiments are repeated for 5 times as the superscript test process. 4) Flow resistance coefficient measure: Computing the flux and the correspondence pressure difference that have been measured through the test to the flow resistance coefficient and the discharge coefficient under different pressure difference.

3 Tests conclusion 1) Cold cyclic test: The leak rate is in the checking of four times under 4.8 cm3/h. 2) Hot cyclic test: Polishing 1 time. The valve is operated to open and close 1 400 times after polishing. The leak rate is in the checking of three times under 4.8 cm3/h. 3) Cold and hot exchange test: Polishing 1 time. After three test cycles, the leak rate is in the checking of valve seat through polishing under 4.8 cm3/h. 4) Flow resistance coefficient measure: The test data are in Table 1.

Table 1 Test data

Parameter Parameter value

Δp (MPa) 1.400 1.432 1.445 1.480 1.525 1.580

ξ (×10－8) 2.295 0.815 0.335 0.006 0.000 8 0.000 1

Flux coefficient (m2, ×105) 5.30 9.10 14.20 105.10 287.0 685.0

170 Annual Report of China Institute of Atomic Energy 2007

Numerical Study on Thermal-Hydraulics Characteristics in In-Hospital Neutron Irradiator

MAO Yu-long, ZHAO Ai-hu, CHEN Yu-zhou

The In-hospital neutron irradiator is a modified miniature neutron source reactor (MNSR) with coolant of de-ion water in natural circulation. A numerical simulation of the flow and heat transfer in this nuclear facility is made using computational fluid dynamic code. The calculation is verified by an integral simulation test with scaling ratio of 1﹕1 and uniform heating, suggesting the predictive capability of the code for the thermal hydraulic behavior in this natural circulation. The flow rate of natural circulation, the distributions of temperature and velocity of the coolant and the temperature of fuel elements in the core are calculated. The water temperature difference between the inlet and outlet of the core, ΔT, increases as the power, P, increasing as ΔT-P0.45. The flow in the core exhibits extremely complicated feature, characterizing the natural circulation, as shown in Fig.1 and 2. During normal operation condition, the boiling will not occur in the core.

Unit：K Fig. 1 Water temperature field in core

Fig. 2 Distribution of cladding temperatures of fuel elements in core a—The first layer；b—The sixth layer；c—The tenth layer FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Science and Technology of Reactor 171

Preliminary Design of Lead-Bismuth Eutectic Thermal-Hydraulic and Corrosion Test Loop

QIAN Yan-yue

A preliminary design of lead-bismuth eutectic thermal hydraulic and corrosion test loop (TCTL) has been performed for further accelerator driven sub-critical system (ADS) studies. TCTL is a middle-scale facility which has a total power of 500 kW. TCTL consists of Pb-Bi loop, vacuum system, cover gas system, cooling water system, oxygen control system, data acquisition and control (DAC) system，and power supply system, etc. The working material of TCTL is 99.5% purified lead-bismuth eutectic which is composed of 45.5% lead and 55.5% bismuth. TCTL occupies 60 m2 and the temperature rise is 100 ℃ while the velocity is 1 m/s. TCTL can be used to carry out experiments on the aspects of thermal hydraulics and chemical corrosion and would be able to meet the requirements for developing ADS techniques in China.

Effect of SiC Nanowires on Flexural Properties of CVI-SiC/SiC Composites

YANG Wen, Hiroshi Araki1, Akira Kohyama2, YANG Qi-fa, XU Yuan-chao, YU Jin-an, Tetsuji Noda1 (1 National Institute for Materials Science, Japan; 2 Institute of Advanced Energy, Kyoto University, Japan)

Continuous SiC fiber reinforced SiC matrix composites (SiC/SiC) are one of the most attractive candidate structural materials for fusion because of their potential advantages for nuclear applications and superior safety characteristics compared with metallic materials. SiC nanowires have great potential for use in composite materials as the reinforcements with very high strength and toughness. In this study, single crystal SiC nanowires with volume fractions (VNW) of 0, 1.6%, 5.7% and 6.1% were incorporated in the matrices of several Tyranno-SA/SiC composites, to study the effects of the nanowires on the flexural properties of the composites. The results show that SiC nanowires are very effective to improve the mechanical properties of SiC/SiC composites (Table 1). With about 6% of nanowires in the matrix, the composite showed near doubled ultimate strength, about 77% increased proportional limit stress, and 64% increased flexural modulus. The efficiency of the SiC nanowires depends on the carbon coating thickness. Several nanometers carbon on the nanowires is not enough for the composite to take full advantages of the strong SiC nanowires. Approximately 50 nm carbon coating can produce sufficient small bonding strength to allow moderate interfacial debonding and pullout of the nanowires from the matrix, resulting in further improving mechanical performance of the composite. With the same amount of carbon coating on the nanowires, the flexural modulus (Ef), proportional limit stress (σPLS) and ultimate strength (σu) increase linearly with increasing volume fraction of the nanowires (Fig. 1).

Table 1 Density, volume fractions of fiber and nanowire, carbon inter-phase thickness and flexural mechanical properties of composites －3 1) Comp. ID Density/(Mg·m ) Vf /% C on fiber/nm VNW/% C on NW/nm Ef /GPa σPLS/MPa σu/MPa FRC 2.70±0.14 About 43 About 60 0.0 － 140±23 370±77 380±113 NRC1.6 2.62±0.03 About 43 About 60 1.6 About 5 171±35 430±34 470±50 NRC5.7 2.62±0.03 About 43 About 60 5.7 About 5 240±35 570±121 660±77 NRC6.1 2.61±0.02 About 43 About 60 6.1 About 50 210±21 670±70 750±103 Note: 1) is volume fraction of Tyranno-SA fiber 172 Annual Report of China Institute of Atomic Energy 2007

Fig. 1 Effect of SiC nanowire volume fraction on flexural modulus, proportional limit stress and ultimate flexural strength of composites

●—Ef/EFRC; ▲—σPLS/σFRC; □—σu/σFRC

Effects of Heat Treatment on Microstructure and Flexural Properties of CVI-Tyranno-SA/SiC Composite

YANG Wen, Hiroshi Araki1, Akira Kohyama2, Tetsuji Noda1 (1 National Institute for Materials Science, Japan; 2 Institute of Advanced Energy, Kyoto University, Japan)

Effects of heat treatment in vacuum on the microstructure and strength of a CVI-Tyranno-SA/SiC composite were investigated. Very thin (20 nm) carbon layer was deposited on the fibers as the fiber/matrix interlayer to modify the interfacial bonding strength. The room temperature ultimate flexural strength UFS (Fig. 1: The UFS was normalized by the strength without heat treatment) showed no degradation at heat treatment temperature up to near 2 073 K, beyond witch the strength decreased with increasing the heat treatment temperature. About 58% of as-fabricated strength maintained even after heat treatment at 2 273 K. Damages to the specimen surfaces and the inner walls of relatively large open pores (Fig. 2) in the specimens that might be caused by the sublimation of the CVI-SiC matrix during the heat treatment, are believed to be the main reason causing the decrease of the strength of the composite. The present CVI-Tyranno-SA/SiC composite showed much improved RT strength and structure thermal stability than the CVI-SiC/SiC composites reinforced with old-generation Hi-NicalonTM fibers (Fig. 1).

Fig. 1 Heat treatment temperature dependence of normalized RT UFSs for CVI Tyranno-SA/SiC and Hi-NicalonTM/SiC composites ○—Tyrano-SA/SiC; △—Hi-Ni calon/SiC FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Science and Technology of Reactor 173

Fig. 2 Damages to specimen surfaces and inner walls of relatively large open pores in specimens a—Surface of specimen after heat treatment at 2 273 K, showing significant damages occurred at the specimen surface; b, c—SEM images from specimen after heat treatment at 2 273 K, showing the formation of a layer of particles at the inner walls of a large open pore in the specimen

Effects of Interlayer and Matrix on Properties of Advanced CVI-SiC/SiC Composites

YANG Wen, Hiroshi Araki1, YANG Qi-fa, Tetsuji Noda1 （1 National Institute for Materials Science, Japan）

The flexural properties and fracture toughness of several SiC fibers/nanowires reinforced SiC matrix composites with various fiber/matrix interlayers have been investigated comparatively. The results (as shown in Table 1 and Fig. 1 are very important to the mechanical properties of the composites. A 120 nm thick carbon interlayer increased both the strength and toughness twofold. When the single carbon interlayer is replaced by a C/SiC/C tri-interlayers but with same total amount of carbon, the composite shows no significant changes of the properties. Preliminary study on the composite with SiC nanowires in the matrix shows that SiC nanowire possesses very high reinforcement efficiency, providing the composite high strength and toughness.

Table 1 Density, interlayers and mechanical properties of composites

－3 1) 1) Composites Density/(Mg·m ) Interlayers/nm Strength/MPa Strength /MPa K1/MPa K1c /MPa C0 2.78±0.01 － 280±60 101 7±1.7 2.5 C100 2.74±0.02 C120 570±26 208 14±4.3 5.1 C110 2.62±0.03 C60/SiC140/C50 520±20 198 15±3.6 5.7 NC60 2.61±0.02 C60 750±103 287 20±2.0 7.7

Note: 1) is strength and toughness modified by density of material

Fig.1 Typical flexural stress-displacement curves 174 Annual Report of China Institute of Atomic Energy 2007

Progress of Advanced UO2 Fuel Pellets Irradiation Program

XU Xi-an, ZHANG Pei-sheng, WANG Hua-rong, GAO Yong-guang, ZHANG Ai-min, -zhe

In-pile test items of advanced UO2 fuel pellets irradiation program were reviewed and approved by national nuclear safety authority. The first power commissioning test was carried out on 15 May, 2007. After an irradiation cycle (10 reactor full power days), the test fuel assembly rotated 180° and another power steps test was conducted on 15 June, 2007. By the end of 2007, eight irradiation cycles (86 Reactor full power days) have been completed and the average fuel assembly burnup has accumulated to about 4 800 MW·d/t.

1 Outline of fuel assembly The test assembly placed in H8 irradiation channel in the SPR consists of 4 fuel rods, one of which has a centre-line thermocouple. Ten sensors are fixed in assembly to monitor the test parameters as follows: 1) Inlet coolant temperature (2 thermocouples); 2) Outlet coolant temperature (4 thermocouples); 3) Fuel centre temperature (1 thermocouple); 4) Neutron flux in fuel assembly (3 SPNDs: N7, N8 and N9).

2 Power commissioning Two times of power commissioning tests were carried out. The reactor power was increased step by step as prescribed steps (1 000, 1 500, 2 000, 2 500, 3 000, 3 500 kW) and each step kept for 10 minutes. In the first test, the fuel rod with the centre-line thermocouple faced the centre of the reactor core. The SPNDs (N8&N9) which are closer to reactor core showed higher neutron flux than the detector N7. In the second test, the layout of the reactor was unchanged but the test fuel assembly turned 180º, the detector N7 gave higher values. The results are shown in Table 1 and Table 2.

Table 1 Result of power steps test (the first test)

Neutron flux/(cm－2·s－1) Power/kW Coolant temperature rise/℃ Fuel centre temperature/℃ N07 N08 N09

1 000 0.8 0.9 0.9 0.23 206

1 500 1.1 1.3 1.3 0.44 301

2 000 1.5 1.7 1.8 0.52 384

2 500 1.8 2.1 2.2 0.65 464

3 000 2.2 2.5 2.6 0.75 549

3 500 2.6 3 3.1 0.89 613

3 Steady-state operations During reactor normal operations, the test parameters were on-line monitored by neutron detectors, fuel centre-line thermocouple and coolant temperature thermocouples. The displayed data could follow instantly the power changes of the irradiated fuel assembly. The measured values are basically stable and are in accordance with analytic calculation. For example, the results during the eighth cycle are shown in Fig. 1.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Science and Technology of Reactor 175

Table 2 Result of power steps test (the second test)

Neutron flux/(cm－2·s－1) Power/kW Coolant temperature rise/℃ Fuel centre temperature/℃ N07 N08 N09

1 000 0.93 0.79 0.76 0.27 175

1 500 1.35 1.15 1.10 0.38 248

2 000 1.83 1.56 1.50 0.52 322

2 500 2.28 1.95 1.86 0.67 389

3 000 2.77 2.37 2.27 0.82 461

3 500 2.95 2.52 2.42 0.87 486

Fig.1 Changes of neutron flux and fuel centre temperature as time

－2 －1 L1——Fuel centre temperature /100 ℃；L2——Average neutron flux (cm ·s )

Microstructural Analysis on JLF-1 Steel Tested by Fatigue Deformation

LI Huai-lin, Arata Nishimura1, Takeo Muroga1, Takuya Nagasaka 1 (1 National Institute for Fusion Science, Toki, Gifu 509-5292, Japan)

A reduced-activation ferritic/martensitic steel, JLF-1, is considered as one of the candidate alloys for the blanket structure components of the fusion reactors. The fatigue properties are important issues for fusion reactor design. Thus, it is important to understand the microstructure change under cyclic deformation. The low cycle fatigue tests (LCF) were carried out at RT, 673 K and 873 K at strain rate of 0.1%/s in vacuum (≤5×10－3 Pa) using engineering size cylinder specimens. Two thermocouples were welded in the gage length on the specimen. The temperature difference of the two thermocouples is kept less than 3 K. The φ3 mm thin foils for TEM were prepared from the base metal and the center of the LCF specimens of total strain Δεt =1.8% at RT, 673 K and 873 K. All the thin foils were polished to less than 0.1 mm in thickness. The temperature effect on fatigue life of JLF-1 is little when fatigue life is plotted against total strain range. However, the microstructure changed significantly. Before fatigue (Fig.1), the JLF-1 is a tempered martensitic steel, the dislocation network was observed, and the dislocation density was very high (ρ=6.4×1014 m － 2). After fatigue at 873 K (Fig.1), the dislocation density decreased significantly (ρ=1.3×1012 m－2). Beside the change in dislocation, the lath width also increased obviously after fatigue at 873 K. The change in microstructure means that increasing the test temperature up to 873 K results in 176 Annual Report of China Institute of Atomic Energy 2007

the complete recovery of the initial tempered martensitic microstructure although the fatigue life is hardly affected by the test temperature.

Dislocation network

14 －2 12 －2 As received ρ=6.4×10 m 851st cycle at 600 ºC, Δεt=1.8%, ρ=1.3×10 m

Fig. 1 Effect of cyclic deformation on dislocation structure of Δεt =1.8% at 873 K

Cyclic Softening Effect on Design Margin of JLF-1 Steel

LI Huai-lin, Arata Nishimura1, Takeo Muroga1, Takuya Nagasaka 1 (1 National Institute for Fusion Science, Toki, Gifu 509-5292, Japan)

A reduced-activation ferritic/martensitic steel, JLF-1, is considered as one of the candidate alloys for the blanket structure components of the fusion reactors. The LCF tests of JLF-1 were carried out at RT, 673 K, and 873 K in vacuum (≤5 mPa) on a servo-hydraulic fatigue testing machine with a dynamic load capacity of ±10 tons.

Change in peak stress during fatigue test at RT, 673 K and 873 K of Δεt=1.8% is shown in Fig.1, which demonstrated the cyclic softening. Cyclic softening is a design issue for RAF/M steels since cyclic softening of materials will reduce the deformation resistance. Figure 2 shows the static stress-strain curves of tensile test and the hystersis curves of LCF tests at around half life at 873 K. If the peak tensile stresses in hysteresis curves were connected, the cyclic stress- strain curve could be obtained. Similar to tensile test, if a cyclic yield stress point was defined as 0.2% strain off-set stress point from zero of cyclic stress-strain curves, the cyclic yield stress could be determined.

In design, a stress for design, Sm, is defined, which is given for instance.

SmyUTS= min{2σ / 3,σ / 3} (1) where the σy and σUTS are yield stress and ultimate tensile stress, respectively. The allowable stresses are

Pm≤Sm (2) According to the formula (1), the stress for design of JLF-1 steel at elevated temperature could be calculated based on the tensile data. Figure 3 shows the change in static yield stress, cyclic yield stress and stresses for design of JLF-1 steel against the temperature. The reduction in design margin is significant when the cyclic softening happens in cyclic deformation. In practical structure, the combined mechanical and thermal cyclic stresses may exceed the stress for design. From the viewpoint of static deformation analysis, the structure is safe if the exceeding stress is below the static yield stress curve. But as a result of cyclic softening, when the exceeding stress is over the cyclic yield stress curve even it is still below the static yield stress curve, the structure will be deformed. If the exceeding in stress happened at 873 K, the deformation will cause disaster. Thus, the phenomenon of cyclic softening of JLF-1 steel is a critical issue for design. Since the ‘cyclic yield stress’ is very useful as a lower bond limit of the cyclic stress, to avoid the misleading, the FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Science and Technology of Reactor 177

‘cyclic yield stress’ could be named as ‘lower cyclic stress limit’. The lower cyclic stress limit curve is a base for design and safety analysis. Furthermore, it should be worth assessing whether the design rules (formula (1) and (2)) derived from the mechanical properties of the materials in its initial tempered martensitic condition still encompass enough safety margin.

Fig. 1 Change in peak stress during fatigue ▲—1.8％, RT; ◇—1.8％, 673 K; ◆—1.8％, 873 K

Fig. 2 Tensile stress-strain curve and fatigue hysteresis curves at around half life at 673 K

Fig. 3 Change in static yield stress, cyclic yield stress and stresses for design of JLF-1 steel against temperature 178 Annual Report of China Institute of Atomic Energy 2007

Radiochemistry and Nuclear Chemistry

Reaction Kinetics of Dihydroxyurea With Nitrous Acid and Its Effect on Stabilizing Pu(Ⅲ)

YAN Tai-hong, ZHENG Wei-fang, YE Guo-an, ZHANG Yu, XIAN Liang, BIAN Xiao-yan, DI Ying

Nitrous acid should be scavenged in the partitioning step of Purex process because it affects the valence of plutonium and other nuclides. Dihydroxyurea (DHU) was found to be a promising reductant to stabilize Pu(Ⅲ). The reaction kinetics of DHU with nitrous acid was studied in HClO4 and HNO3 1 0 media. The reaction rate equation is expressed as v＝－dc(HNO2)/dt＝kc (HNO2)c (DHU)· －0.15 + 0.15 －0.15 －1 c (H ). In HClO4 and HNO3 media, the reaction rate constants are (2.37±0.04) mol ·L ·min at t＝15 ℃, I＝0.5 mol/kg and (1.29±0.06) mol0.15·L－0.15·min－1 at t＝10 ℃, I＝0.5 mol·kg－1, respectively. The reaction rate constant decreases slightly with the increase in ion strength. The effect of temperature on the reaction rate was also studied and it is found that the reaction rate increases quickly with the increase in temperature. The reaction activation energies are 68.2 kJ/mol and 76.8 kJ/mol in

HClO4 and HNO3 media, respectively. In 0.5-3.0 mol/L nitric acid solutions, excess DHU can stabilize Pu(Ⅲ) well over 48 h.

Pu(Ⅳ) Reduction and U/Pu Split in Purex Process by Dihydroxyurea

YAN Tai-hong, ZHENG Wei-fang, YE Guo-an, ZHANG Yu, XIAN Liang, YANG Su-liang, DI Ying, BIAN Xiao-yan

The reduction of Pu(Ⅳ) by dihydroxyurea (DHU) was investigated using UV-V is spectrophoto- meter. The results show that DHU can reduce Pu(Ⅳ) to Pu(Ⅲ) rapidly. DHU has little influence on the distributions of U(Ⅵ) and HNO3 in 30%TBP/kerosene(OK)-HNO3 system. The reduction back- extraction behavior of Pu(Ⅳ) in 30%TBP/OK was firstly investigated under conditions of different temperatures, different concentrations of DHU and HNO3 and various phase contract time, respectively. The results (Table 1) show that Pu(Ⅳ) in organic phase can be stripped rapidly to aqueous phase by DHU. Simulating the 1B contactor of the Purex process by DHU with nitric acid solution as the stripping agent, the separation factors of uranium/plutonium can reach 2.1×104. This indicates that DHU is a promising salt free agent for uranium/plutonium separation.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 179

Table 1 Experimental results simulating 1B contactor

－1 －1 Simulating 1B contactor ρ(Pu)/(mg·L ) ρ(U)/(g·L ) SFPu/U SFU/Pu Material balance of Pu/%

4 5 1AP 247 89 2.1×10 5.8×10 101.1

1BP 1 049 0.65

－4 1BU 4.1×10 72.5

Formic Denitration for Recovery of Plutonium

HE Hui, , HUANG Xiao-hong, CHANG Shang-wen

In order to extract plutonium with TBP from wastewater, the nitric acid concentration must be controlled from 3 to 6 mol/L. The concentration of nitric acid, which is about 12.8 mol/L in the existing waste water, has to be reduced before recovery of plutonium with TBP. Firstly, formic acid is selected as reducing agent for denitration in model solution. The results show that nitric acid and formic acid can react peacefully in condition of condensation and regurgitant when formic acid drops into the reaction system in appropriate speed and the temperature is controlled about 95 ℃ . The concentration of nitric acid can be decreased to 3.5-3.9 mol/L from 12.8 mol/L and the mol rate between nitric acid and formic acid is about (1.1-1.2)﹕1. Then, the real system, in which plutonium concentration is about 0.8 g/L, is treated and the concentration of nitric acid is 4.2 mol/L after formic denitration. When 30%TBP-kerosene is selected as organic phase and the phase ratio is 1﹕1, the recovery rate of plutonium can reach 94.4% after 1 time extraction and 99.7% after 3 times extraction.

Oxidation of Pu(Ⅲ) With Liquid Tetroxide-Dinitrogen

LI Gao-liang, HE Hui, TANG Hong-bin, CHEN Hui, ZHENG Wei-fang, WANG Liang

It is the first time of N, N-dimethylhydroxylamine (DMHAN) and monomethyl-hydrazine (MMH) used to the advanced nuclear fuel reprocessing process. One purpose of this process is to reduce the amount of solid radioactive waste produced in this process. Sodium nitrous as oxidant of Pu(Ⅲ) was used in this process previously, it would introduce a lot of solid radioactive waste. It is feasible of N2O4 in place of sodium nitrous used as oxidant of Pu(Ⅲ) in this process. In order to purify Pu by extraction, the products, Pu(Ⅲ), containing DMHAN and MMH, from U-Pu split cycle in Purex process should be oxidized into Pu(Ⅳ) by N2O4 without introduction salt into the Pu solution. Therefore, the oxidation of

DMHAN and MMH by N2O4 is necessary to be investigated. The results show that the amount of tetroxide-dinitrogen needed to oxide the reductants are about two times of the reductants. The Pu(Ⅳ) proportion can exceed 99.9% after the oxidation with liquid tetroxide-dinitrogen, which can meet the target of the schedule. Finally, the oxidation condition is concluded that to pour 2.5 times of the reductants’ tetroxide-dinitrogen into the feed and mix round slowly. This condition is feasible when the concentration of nitric acid is at 0.5-2.0 mol/L and the temperature is at 5-40 ℃ . 180 Annual Report of China Institute of Atomic Energy 2007

Interfacial Reactive Kinetics of Back-Extraction of Np(Ⅳ) From 30%TBP-OK With Acetohydraxamic Acid

ZUO Chen, YAN Tai-hong, ZHENG Wei-fang

Interfacial reactive kinetics of the back-extraction of Np(Ⅳ) from 30%TBP-OK with acetohydra- xamic acid (AHA) has been investigated using a Lewis cell. The experimental results are as followings (Fig. 1). 1) By changing the stirring speed, temperature, interfacial area it was suggested that back- extraction process of Np(Ⅳ) from 30%TBP-OK with acetohydraxamic acid is controlled by interfacial chemical reaction when the stirring speed is higher than 160 r/min. 2) The different parameters affecting the back-extraction rate such as Np, TBP, nitric acid, nitrate, AHA concentrations were separately studied. The initial back-extraction rate of Np(Ⅳ) was expressed to be R＝kco(Np). The experimental results show that back-extraction rate as a function of Np concentration from 0.1 mol/L to 1.0 mol/L in organic phase is first order, when it is zero order with respect to the other investigated parameters such as the TBP concentration in organic phase, the nitric acid concentration and the nitrate concentration in aqueous phase. The AHA concentration from 0.005 mol/L to 0.100 mol/L also have no influence on back-extraction rate, but back-extraction rate drops largely as there is no AHA in aqueous phase.

2+ + Fig. 1 Cyclic voltammograms of NpO2 /NpO2 in nitric acid media at platinum electrode Scan rate, V/s: 1—0.01; 2—0.02; 3—0.03; 4—0.04; 5—0.05; 6—0.07; 7—0.09

Electrochemical Behavior of Np(Ⅵ)/Np(Ⅴ) Ions in Nitric Acid Solutions at Platinum Electrode

ZHANG Hu, YE Guo-an, QIAO Ji-xin

4+ + 2+ Neptunium exists in the nitrics acid solution of the Purex process as Np , NpO2 , NpO2 ions. Among these different valency states of neptunium, Np(Ⅳ) and Np(Ⅵ) is extractable by TBP while Np(Ⅴ) is unextractable. It is necessarily to control valency states of neptunium if Np needs to be FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 181

separated. The electrochemical procedure without any reagents can be used to control the valency of Np. Electrochemical behavior of Np(Ⅵ)/Np(Ⅴ) ions was investigated in nitric solution by potential cyclic sweep voltammetry on platinum electrode. The CV results imply that the electrochemical oxidation reactions of Np(Ⅳ)/Np(Ⅴ) are quasi-reversibly. The kinetics parameters of electron transfer coefficient α are 0.69, diffusion coefficient + －6 2 0 －3 D of NpO2 are 1.42×10 cm /s and standard rate constant k are 1.54×10 cm/s.

Computer Simulation of Co-decontamination Process in Purex

HE Hui, LI Gao-liang, CHEN Hui, JIANG De-xiang, TANG Hong-bin

Based on the theory of cascade extraction, a computer program has been established in order to simulate the steady state approach model of co-decontamination process in Purex. Through changing the input of the flux and component of the feed stream (1AF), extratent stream (1AX) and scrubbing stream (1AS), the security analysis and extraction optimization have been estimated by the computer calculation and it is found that the recovery of uranium and plutonium is remarkably effected by the flux shift of 1AF and 1AX except for 1AS: increasing the acidity of 1AS can realize a flexible operation of 1A while can lead to a bad decontamination of U product against RE.

Radiolysis Stability of Hydroxyurea

XIAN Liang, ZHANG Bai-qing

Hydroxyurea (HU), as a novel salt free reducing agent, is a strong hydrophilic reagent and stable in

HNO3 solution. HU can reduce Pu(Ⅳ) quickly. HU can also scavenge the HNO2 quickly and stabilize

Pu(Ⅲ) in HNO3 system. The former study indicates that the HU is a good reductant in the U/Pu split. In this work we studied the γ-radiolysis stability of HU. The experiment result shows that HU concentration has little changed at the dose of 5-10 kGy in H2O system. At the dose of 25, 50 and

100 kGy, the percentage of radiolysis of HU is 15%, 52% and 59%, respectively in H2O system. The percentage of radiolysis increases with the increase of nitric acid concentration. In 2.9 mol/L

HNO3 solution, the percentage of radiolysis is higher than 50% at the dose of 25 kGy or beyond.

Electrooxidation of Pu(Ⅲ) in 1BP Solution

ZHANG Hu, YE Guo-an, LI Li, LI Gao-liang, ZHENG Wei-fang

In the Purex process, the plutonium product is obtained as Pu(Ⅲ) nitrtate in nitrica acid solution 182 Annual Report of China Institute of Atomic Energy 2007

with rest of N,N-dimethylhydroxylamine (DMHAN) and Monomethyldrazine (MHA) after first plutonium extraction cycle. Prior to re-extraction, plutonium must be completely reoxidized to Pu(Ⅳ). At the same time the chemical reagents of DMHAN and MHA have to be destroyed. This process is carried out in existing facilities by addition of sodium nitrite or by passing NO2 gas through the product solution. The use of NaNO2 give rises to additional salt in the waste. NO2 has the disadvantage that a great excess is often needed and an effluent NOx loaded with alpha and beta active aerosols is produced. The method of electrooxidation without added chemicals is a clear and environmental technology, this method produces almost no waste, and the process can be operated automatically and remotely. In this working, the method of electrooxidation is studied by controlling current density, potential and nitrics acid concentration. After electrooxidation, the Pu(Ⅳ) proportion can exceed 99.7% and the Pu(Ⅵ) proportion is less than 0.3%.

γ-Radiolysis of N, N-dimethylhydroxylamine and Methylhydrazine

CHEN Hui, HE Hui, LI Gao-liang, YE Guo-an

The purpose of this work is a preliminary investigation on γ-radiation of N, N-dimethylhydroxy- lamine (DMHAN) and methylhydrazine (MMH). The absorbed dose in Purex process is calculated. The relation of the absorbed dose and the wastages of DMHAN and MMH are given respectively. By ion chromatography, gas chromatography and UV spectrophotometry, the gas and liquid compositon, which are produced by radiation degradation of DMHAN and MMH at different condition, were studied. The main compositions of radiolysis products of DMHAN and MMH are formaldehyde methanol hydrogen and methane. The results indicate that the wastages of the salt-free reagents increase with the increasing absorbed dose (Fig. 1). At the absorbed dose of 150 kGy, the radiolysis degree of DMHAN is less than 2%, the rest concentration of DMHAN can ensure the yield of Pu meets the process requirement. For the γ-irradiation stability, DMHAN is suitable in the 1B process.

Fig. 1 Wastage of DMHAN at various radiation doses

□—c0(DMHAN)=0.1 mol/L, c0(HNO3)=0.3 mol/L；●—c0(DMHAN)=0.8 mol/L, c0(HNO3)=0.2 mol/L FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 183

Analysis of N, N-dimethylhydroxylamine by Gas Chromatography

LI Gao-liang, HE Hui, CHEN Hui, YE Guo-an

The application of salt-free reagents in the spent fuel reprocessing process was recognised in recent years. N, N-dimethylhydroxylamine (DMHAN) can reduce Pu(Ⅳ) to Pu(Ⅲ ) quickly and it is feasible used as reductant of Pu(Ⅳ) in the spent fuel reprocessing process. The determination of DMHAN in water and nitric acid by capillary gas chromatography has been studied. The result shows that the linearity is excellent in the range 3.0×10－4-2.5×10－3 mol/L with correlation coefficient over 0.999 (Fig. 1 and 2). Relative standard deviation (RSD) of samples is lower than 1.0%. Minimum detectable limits (MDL) of DMHAN is 3.0×10－4 mol/L. The present impurities such as methanol, formaldehyde, methanoic acid, nitric acid, monomethyl hydrazine, ethanol, hydrazine, methylamine do not effect on the determination of DMHAN in the analytical system.

Fig. 1 Gas chromatogram of DMHAN

Fig. 2 DMHAN correction curve of peak area against concentration

184 Annual Report of China Institute of Atomic Energy 2007

Application of Treating Organic Waste From Purex Process Using Supercritical Water Oxidation

WANG Liang, HE Hui, TANG Hong-bin

Supercritical water oxidation (SCWO) technique, which is developed with supercritical water as its reaction medium, becomes a hot topic of research dealing with organic waste recently because of several advantages such as speedy reaction, thorough oxidation and simple equipment. In nuclear industry, there are a lot of organic wastes be produced. Traditional techniques have some limitation to deal with the wastes. So, France, America and Japan put a great energy to SCWO technique. Especially the Toshiba Corporation, have used the technique in laboratory to deal with the waste of liquid scintillation counter cocktail, TBP and resin. Text revealed that 99% or more TBP and silicone oil was decomposed at 673 K and 30 MPa, and 93% liquid scintillation counter cocktail can be decomposed at this condition. This paper introduces the principium and prominent characteristics of SCWO technique including the developing situation over the world, then discusses the great prospect of this technique in nuclear industry mainly and at last, arrives at a conclusion that SCWO technique will be a method with great potential in dealing with TBP, kerosene and resin waste in the Purex process.

Development of Big Flow Ratio Micro-mixer-settler Extractor

CHANG Shang-wen, OUYANG Ying-geng, WANG Xiao-rong

It is necessary for the 1BBX extractor to testify the technology of plutonium obstructed extractor in intermediate scale testing plant and to optimize for the subject of 2-3 flow frame warm testings of inter- mediate scale testing plant in nuclear energy exploiting. According to the determinate flow ratio, 30﹕1, we designed the micro-mixer-settler extractor. For the re-extraction requirement of big flow rate, 30﹕1, of organic and aqueous, we designed the micro-mixer-settler. In the agitating room, the aqueous phase which is introduced by the aqueous outlet of φ3 mm×0.5 mm stainless steel tube and the partial aqueous phase in the separated room through the agitation were mixed with the organic phase. Therefore, the same grade aqueous can be used repeatedly to ensure the constant phase rate. Meanwhile, when there is lack of aqueous, the same grade organic phase can also be introduced into the agitating room to be taking countercurrent re-extraction with reflux so that to increase the re-extraction efficiency. Mixing diagram of aqueous and organic phase is shown in Fig. 1. The mixing is to adopt the mini-type motor. The volume of the agitating room and the separating room are 2 mL and 7 mL, respectively, and the extractor has 6 stages, the total volume is 54 mL, and the mechanical agitating is driven by the micro-electromotor. We have performed the following test such as filling the extractor with nitro acid, and the hydraulic tests of which the phase ratio of organic phase, kerosene and the aqueous phase, 2 mol/L nitro acid is FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 185

1﹕1 and 30﹕1, respectively. These experiments indicate that the mixer-settler could reach to the design requirement. But there are several lacks as follows: the first is the high surface tension caused by the aqueous outlet of φ3 mm×0.5 mm stainless steel tube against nitric acid, and it reduces the fluid mobility; the second is the low machining accuracy of the extractor, and it results in the inadequate rotating speed and unsatisfactory phase splitting effect, and then is the easy chocked outlet of the aqueous phase. Now we are preparing for the big flow ratio test and the acid balance test with nitric acid of 2 mol/L and the 30％TBP, kerosene after these factors resolved.

Fig. 1 Mixing diagram of aqueous and organic phases

Flow Measurement and Feedback Controlling in Bench Test Equipment

GUO Jian-hua, LI Wei-min, OUYANG Ying-gen, GAO Wei, LIU Li-sheng, CHANG Shang-wen, LI Rui-xue, CHANG Li

In the bench test, it is very important for the measurement and control of fluid flow to ensure the steady operation of the mixer settler and well carrying out experiment, so it is necessary to study a method to detect and control the fluid flow. Based on the improvement of the Bronkhorst thermal mass flow meters made in Netherlands and frequency control pump made by ourselves, online measurement and feedback controlling system adapted to the bench test equipment has been accomplished by cooperation with software company. It is a set of high performance industrial automation software which can complete on-site data gathering, process visualization and process monitoring. Furthermore, the system can achieve the following subject such as real time detection and display of the flow data, conservation and analysis of the historical flow data, dynamic setting and error setting of the normal flow rate, dynamic setting of the measurement frequency, control of the pump by closed-loop control frequency through the error feedback controlling system, multipoint measurements, which can measure and control eight points by one computer, and the graphical interface design. These make the operator to be clear at the measurement object. The composition of measurement and feedback controlling system of flow rate data is shown in Fig. 1. All equipments were set up and demonstrated with the deionized water as feed. The research on output stability of flow rate was conducted. 0.025% of relative standard deviation was obtained for the output data of flow rate at intervals of 1 min. 186 Annual Report of China Institute of Atomic Energy 2007

Fig. 1 Composition of measurement and feedback control system of flow rate data

Research Progress in Pulse Extraction Column

ZHANG Bai-qing

HETS or HTU is reduced a lot, and the mass transfer efficiency is higher in pulsed extraction column (PEC) than in common extraction column driven only by gravity, because pulse can improve the performance significantly in normal packed column and sieve plate column. The rapid reciprocating pulsation of the fluid in column can not only crush droplets leading to more contact area between two phase, but also increase fluid turbulence and improve two-phase contact. At the same time, there are not moving parts and bearings in a pulse stirring column, so it has a lot of advantages in dealing with corrosion-strong radioactive materials. PEC has a wide range of applications in the spent fuel reprocessing already. PEC is prospective in future. The main kinds of PEC include pulsed packed column, pulse-sieve plate extraction column and doughnuts pulsed extraction column. The present research concerns in the PEC’ basis parameters, extraction principle, the operating conditions of stability area, material handling capacity of the border, the process conditions of extraction column for different nuclides and so on. Former research shows that 0.5-2 Hz is the common pulse frequency, and the amplitude is in the range of 1.3-5 cm. The comprehensive column performance can be obtained for the PEC with aperture of 3.2 mm, the hole rate of 23% and the board spacing of 50 mm.

Adsorption of Se, Zr and Pd by Glass, Quartz and Polyethylene at Trace Level

LIANG Xiao-hu, DING You-qian, YANG Jin-ling, CUI An-zhi

With an increasing consciousness of environmental protection, people has pay more and more attention to the nuclide of long term radioactive especially 79Se, 93Zr and 107Pd, in most cases of radiochemical separation and detection, these nuclide are at trace level. The present work is to investi- FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 187

gate the adsorption behavior of these nuclides on the materials mentioned above, and supply more data as reference to the experiments design and operation. 75Se, 95Zr and 109Pd were used as tracer with the concentration of Zr, Se at 8 μg/L, and Pd at 1.2 mg/L approximately, adsorption of the three nuclides under varied acidity of nitric acid and hydro- chloride acid was investigated. 75Se and 109Pd were produced by irradiating the pure powder in element state; 95Zr was acquired by the irradiation of concentrated 235U with a bounty of 90%, then separated by a process: column separation by silicon germ -TBP extraction-column separation by silicon germ. Solution of the three element mentioned above was prepared in nitric acid and hydro-chloride acid media, the concentration of often meet in experiment is 0.1, 0.2, 0.5, 1.0 and 2 mol/L, respectively. The materials being tested were vials made into cylinder shape ,with a flat bottom and a inner diameter of 1 cm. When the experiment begin, 1 mL of the solution were added into the vial, then sealed the vial with polyethylene membrane and stayed there at least 18 h, after that, the activity were determined by an NaI(Tl) γ-instrument, the following step is to empty the solution immediately, washed by the deioned water 1 mL twice, then determined the activity again, the ratio of the two can reflect the adsorption behavior of the nuclides. The results show that these three materials have no interest in absorbing Se in both the nitric acid and hydro-chloride acid media, Pd was not absorbed at that concentration by the materials either in hydro-chloride acid media, the investigation of being in nitric acid media is undergoing. However, these three materials showed, to some extent the interesting in absorbing Zr, and the ability is glass>quartz> polyethylene. This investigation of the three nuclides is all in acid media, as the situation of base media, it still need more study.

Measurement of 90Sr in Soil Samples With Pure Instrumental Method

SUN Hong-qing, ZHANG Sheng-dong, MA Peng, TANG Pei-jia

In order to measure the content of 90Sr in soil sample rapidly, we develop a method to determine the content of 90Sr by measuring the bremsstrahlung generated from the interaction between the high-energy β-particle with the energy of 2.8 MeV from the decay of 90Y who is the daughter nucleus of 90Sr and soil medium. The same as gamma ray, the bremsstrahlung also has the high penetrating effect, so we can measure the bremsstrahlung by an HPGe gamma ray spectrometer. There are two kind of radioisotopes in soil: one is the naturally occurring isotope (U, Ra, Th, and K) and their daughter nucleus; the other is fission produce 137Cs, activation produce 60Co and transuranic

Table 1 Detection efficiency of 90Sr in soil

No. Mass/g Activity/Bq Energy range/keV Efficiency No. Mass/g Activity/Bq Energy range/keV Efficiency

1 50 500 15-290 0.005 223 7 241 2 410 15-290 0.002 708

2 75 750 15-290 0.004 687 8 250 2 500 15-290 0.002 554

3 100 1 000 15-290 0.004 238 9 300 3 000 15-290 0.002 252

4 125 1 250 15-290 0.003 823 10 340 17 000 15-290 0.002 057

5 150 1 500 15-290 0.003 520 11 352 3 520 15-290 0.002 042

6 200 2 000 15-290 0.002 925 188 Annual Report of China Institute of Atomic Energy 2007

241Am. The gamma ray from this nucleus will cause interference for measuring the bremsstrahlung effect in the low-energy range. The key technology is shown as follows: we need to determine the detection efficiency of bremsstrahlung in soil with different mass thickness and deduct the influence from interference nucleus. Therefore, first, we determine the detection efficiency of 90Sr-90Y in standard soil by a broad energy HPGe detector as shown in Table 1; second, it’s needed to measure the influence factor Ri of interference nucleus in soil sample as shown in Table 2; lastly, base on the influence factor Ri to deduct the count from the contribute of interference nucleus in the region of bremsstrahlung energy. After deduct the background and influence of interference nucleus, we will obtain the content of 90Sr in soil by measuring the bremsstranlung with a broad energy HPGe detector, compared with the content of 90Sr in soil sample we have joined interiorly, it is coincident within the error of 10%, so we can determine the content of 90Sr in soil by this developed method.

Table 2 Influence factor Ri of diversified nucleus

Characteristic Ri of energy range Characteristic Ri of energy range Nucleus Nucleus peak/keV (15-290 keV) peak/keV (15-290 keV)

137Cs 661.7 2.94 40K 1 460.8 4.95

60Co 1 332.5 5.61 Th series 583.2 41.05

241Am 59.5 1.68 U-Ra series 351.9 15.41

Influence of Pulse Plating Parameters on Electrodeposition of Uranium

YANG Chun-li

There are three adjustable parameters for the pulse plating: frequency ( f ), occupation ratio (R) and average current density (Jm) .The procedure of electrodeposition can be changed at the same time, the quality of the coating can be improved through changing the wave pattern and the adjustable parameters of pulse plating. In order to find the optimum plating conditions for the actinides, the influence of pulse plating parameters on the electrodeposition of uranium was investigated. The parameters is usually preset and influence the procedure of the plating simultaneously. Thus, it is necessary to find the optimum combination of the three parameters to improve the plating yields and the quality of the coating. In order to investigate the parameters, the orthogonalization selection method was applied. First of all, the weight factor of the parameters was determined by the range with orthogonalization method. Secondly, we changed certain parameter and fixed another to investigate the parameters of pulse plating respectively.

According to orthogonalization selection method, four parameters including f, R, Jm and the deposition medium were appointed as the factors which have three levels respectively. The results are listed in Table 1 (the date in the table indicates yields). The ranges of f, Jm and the deposition medium are same on the whole, but the range of R is only 2.8. The different range proved that f, R and medium influenced the yields far more greatly than R. The level of R changed a little when R varied from 10% to

30%. The level of Jm reached the highest when Jm was 20 mA. When Jm is higher than 20 mA the quality of coating became worse, while Jm is below of that, the yield declined. For elctrodeposotion medium, isopropanol has better yields than DMF, but the firmoviscosity of the coating is better when FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 189

deposited in DMF than in Isopropanol. All of the results accord well with former experiment. In conclusion, the better pulse plating conditions for uranium is f=800 Hz, R=20% or 30% and

Jm=20 mA. The DMF is the suitable solvent. After the orthogonalization selection, a series of experiments were carried out with only one of the parameters changed and other plating conditions fixed. The results are shown in the Fig. 1-3. From the figures, we can see the relationship between the mass thickness and the parameters. Finally, the optimum pulse plating conditions for uranium are determined f=800 Hz, R=30% and Jm=20 mA.

Table 1 Results of orthogonalization selection method

Parameters Level/% Range/% Parameters Level/% Range/%

f, Hz 800 77.69 28.38 Jm, mA 5 56.83 25.56

1 200 49.31 10 51.32

1 500 58.02 20 76.88

R, % 10 60.34 2.80 Medium Isopropanol 25.56 27.17

20 61.45 DMF 67.21

30 63.23 Isobutanol 45.32

Fig. 1 Influence of frequency on mass thickness

Fig. 2 Influence of occupation on mass thickness Fig. 3 Influence of current on mass thickness

190 Annual Report of China Institute of Atomic Energy 2007

Study on Measurement of 93Zr

YANG Jin-ling, ZHANG Sheng-dong, DING You-qian, CUI An-zhi. SHU Fu-jun, WANG Tong-xing

93Zr is produced by nuclear fission and neutron activation of the stable isotope of 92Zr. As it has high fission yield among all the fissionable materials, more attention should be paid when high-level radioactive wastes are dealt with. But up to now, it is deficient in nuclear data of 93Zr. In order to supply samples for measuring its nuclear data, a radiochemical procedure and measurement of 93Zr needs to be developed. First, 93Zr is get from a irradiated test fuel element of Qinshan Nuclear Power Plant using a silica gel adsorption combined with the TBP extraction method. As it is a long-lived (1.53×106 a) pure β-particle-emitting radionuclide, with energy of 60.6 keV (97.5%) and 91.4 keV (2.5%), the activity of the sample got is very low. In order to eliminate influence of self absorption and to improve counting efficiency, we used liquid scintillation spectrometry. But quench is a difficult problem of this method. Acidity and volume of our sample are high spot reviewed. The results show that higher acidity and larger volume of the sample leads to severer quench. Considering the 93Zr standard solution is not available and the maximal β energy of 63Ni is close to that of 93Zr, we use the 63Ni standard to replace the 93Zr to scale the efficiency when we measured the activity of 93Zr with liquid scintillation spectrometry. Then the efficiency should be calculated from the quench-efficiency curve. In order to measure the number of 93Zr atom with MC-ICP-MS, the optimization parameters were achieved, such as collision gas flow rate and ion lens system. Because we have no isotopic thinner of Zr, it is impossible to realize quantitative analysis using this method. So specification curve method is applied. According to the concentration and signal of 90Zr in standard solution, we get its specification curve. Then 90Zr and 93Zr of the sample solution was measured. After ratio of 90Zr and 93Zr was modified, concentration of 93Zr can be obtained. The formulas used to modify the ratio are:

Rtrue＝KRmeasurement (1) β K＝(M/M1) (2)

β＝ln(Rtrue/Rmeasurement)/ln(M2/M1) (3) At last we applied these methods to measure the activity and concentration of the sample.

Spectrophotometric Determination of Lanthanides in Solution

WANG Xiu-feng, DING You-qian, CUI An-zhi

This work is the analysis part which serves for the work concerned in group separation of lanthanides and actinides. The used spectrophotometer is LabTech UV1000/1100, it can scan the maximum absorption wavelength of the sample. Arsenazo Ⅲ was used as color reagent. 1) Analysis process FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 191

After diluted the sample to the concentration range can be analyzed, took 1 mL solution sample to a 10 mL volumetric flask, added 0.4 mL ascorbinic solution with the concentration of 10 g/L and a drop of thymol blue alcohol solution with a concentration of 1 g/L, using NaOH solution as a regent adjust the solution color to a yellow one, then 1 mL 0.01% arsenazo Ⅲ solution was added and the rest was filled to the volume mark by the potassium hydrogen phthalate-hydrochloric acid medium at pH＝2.8, sample blank was used as reference. When scanning and selecting the maximum adsorption of the wavelength, we found that the maximum adsorption wavelength changed when the concentration has changed, so the working curve we made are all the point using the maximum adsorption wavelength each standard sample has, and when a sample is to determine, the maximum adsorption wavelength should be scanned and selected, then the adsorption value was determined and the concentration of the sample was acquired using the working curve. 2) Acquiring the working curve The lanthanides sample solution including all the 14 elements with the purity of 3N (99.9%) or 4N (99.99%) was prepared at exactly the concentration of 1 mg/mL, then a 1 mL prepared solution was drew into a volumetric flask ,then diluted into the concentration of 100 μg/mL, the following step was to draw the 100 μg/mL solution with the volume at 100, 300, 500, 700 μL into four 10mL volumetric flask respectively, added 0.4 mL ascorbinic solution with the concentration of 10 g/L and a drop of Thymol blue alcohol solution with a concentration of 1 g/L, using NaOH solution as a regent adjust the solution color to a yellow one, then 1 mL 0.01% arsenazo Ⅲ solution was added and the rest was filled to the volume mark by the potassium hydrogen phthalate-hydrochloric acid medium at pH＝2.8, so the standard sample solution was prepared with the concentration of 1.0, 3.0, 5.0 and 7.0 μg/mL, respectively. Take 1 mL 100 μg/mL solution and diluted it into a 10 μg/mL one, then draw 500 μL the 10 μg/mL one into a 10 mL volumetric flask, after that a 0.5 μg/mL standard sample solution was make using the steps mentioned above. Using reagent blank as the reference to determine the maximum adsorption of each standard sample, acquired the adsorption value to draw the working curve of adsorption value-concentration. The working curves of each element were showed by the following chart, it shows that the slops of the 11 elements from La to Er are very similar within the error range, slops of Tm, Yb and Lu are 10% lower compared with the others, and the reason lead to this consequence is needed further study.

Production and Separation of 101Tc

YOU Xin-feng, ZHANG Sheng-dong, -hong, DING You-qian, CUI An-zhi

In order to measure it’s nuclear data precisely, the present study concerns in the produce 101Tc by neutron irradiation of natural MoO3 based on the reaction and decay: and then separate trace nucleus 101Tc form milligram Mo. The two different ways of separation, TEVA resin and α-benzoin oxime extraction were studied, and then radiochemical pure 101Tc product was obtained. According investigation, TEVA resin is practically a specific reagent for Tc, kinetics distribution

(Kd) of element Tc on TEVA resin is decreasing with increasing concentration of HNO3. Kd is greater than 3 000 in the case of 0.1 mol/L HNO3 while Kd is only about 10 in 3 mol/L HNO3. The Kd of 192 Annual Report of China Institute of Atomic Energy 2007

element Mo on TEVA resin was determined, compared with Tc, within different concentration of HNO3, and shown in Fig. 1. From the curve, Kd of element Mo on TEVA resin grows up with increasing con- centration of HNO3, comparing with Tc oppositely. In the study, the deed of Mo on TEVA resin column is studied in HNO3 solution, the resin size 100-150 μm, column size φ3 mm×5 mm, operation flow rate

0.5 mL/min. Prior to use, TEVA resin column was preconditioned with 2 mL of 0.1 mol/L HNO3, and then 0.5 mL of 1 mol/L HNO3 Mo sample solution was passed through it. Next 5 mL of 1 mol/L HNO3 were directly flow through the column. Finally, Mo was eluted with 3 mL 3 mol/L HNO3, collected the elution to measure by spectrophotometric method. The quantity of Mo is 4.97 μg and calculated the decontamination factor (DF) of Mo is about 1.2×103 in this procedure.

In the study, Kd of element Mo and Tc on TEVA resin in NaOH solution was also studied, the result is shown in Fig.2. From the Fig.2, Kd of element Mo in NaOH solution is decreasing with the concentra- tion increasing while element Tc have a top point in 0.5 mol/L. Anyway the Kd of Tc is 5 000 minimum, much greater than Kd of Mo, about 10 in 2 mol/L. Compared with HNO3 solution, NaOH solution separation procedure was studied as following: 0.336 68 g 99Mo-99Tcm radioisotope indicator mixed with 0.5 mL of 150 g/L (NH4)6Mo7O24·4H2O carrier solution, shake few minutes, and then sample solution was directly passed through the TEVA resin column (φ3 mm×20 mm) was preconditioned with 4 mL 2 mol/L NaOH solution. Next Mo was scrubbed down with 4 mL 2 mol/L NaOH solution, and then 2 mL deion- ized water passed through the TEVA resin. Finally, the Tc in the column was eluted 99 m with 4 mL 3 mol/L HNO3 solution. The eluation was collected for measurement of Tc by HPGe detector. DF of Mo is greater than 1 000 and the recovery of Tc is 72% in the procedure.

Fig. 1 Kd of element Mo vs. HNO3 concentration Fig. 2 Kd of elements vs. concentration of NaOH solution

In investigation, α-benzoin oxime is practically a specific reagent for molybdenum. In the study, the Kd of Tc between the α-benzoin oxime/ethyl acetate and HNO3 solution (0-5 mol/L) was researched 101 and 0.8-1.0 mol/L HNO3 solution was chosen optimally. In this case, Tc produced by irradiation in minimum neutron source reactor was separated form 101Mo. The following was the separation procedure:

0.5 mL 150 g/L (NH4)6Mo7O24·4H2O sample was enveloped into PVC small vial, and then piped into the min-reactor irradiated approximately 20 min at a neutron fluence rate of 9.0×1011 cm－2·s－1, cooled 101 12 min, and then picked up sample and mixed with 3.5 mL of 1.0 mol/L HNO3, next Tc was extracted from the target material by 4 mL 40 g/L of α-benzoin oxime/ethyl acetate extraction solvent in 50 mL of separatory funnel about 2 min, and then repeated the extracted again and collected the clear liquid phase under layer to measurement in HPGe detector. Form the γ-ray spectrum (Fig. 3), 101Mo and other radioactive nuclides are not detected, DF of Mo is calculated to be greater than 104 by this way. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 193

Fig. 3 101Tc sample spectrum

Separation and Purification of Plutonium From High-Level Liquid Waste

ZHAO Ya-ping, MAO Guo-shu, -ru, CUI An-zhi, ZHANG Sheng-dong

In order to measure the concentration of Pu in one high-level liquid waste (HLLW), anion ion exchange method combined with extraction method are used to separate and purify the element of Pu from HLLW. A series of influence factors are studied such as kind of resins, flow rate, methods of increasing the chemical yield, methods of conditioning valence of Pu and Np, extraction action of Pu with 0.1 mol/L trioctylphosphinic (TOPO)/cyclohexane, decontaminated experiments of some nuclides. According above works, a radiochemical procedure is developed as follow. 1) Column: the size of column is φ3 mm×35 mm with the resin type of N256 (40-200 mesh) resin, washing the column by 5 mL 7.1 mol/L HNO3 solution, with flow rate of 0.1 mL/min.

2) Adjusting valence and acid: adjusting a quantity of HLLW to the medium of 1 mol/L HNO3 solution, adding a quantity of 1 mol/L Fe(NH2SO3)2 to deoxidize Plutonium from Pu(Ⅳ) and Pu(Ⅵ) to

Pu(Ⅲ), at the same time deoxidize neptunium to Np(Ⅳ ), 10 min later, adding superfluously NaNO2 and

Fe(NO3)3 to maintain the medium of 1 mol/L HNO3-0.5 mol/L NaNO2-0.01 mol/L Fe(NO3)3, 10 h later, heating the solution 20 min at 60 ℃ , thus maintain the state Pu(Ⅳ) and Np(Ⅴ ), lastly, adjusting the acid to 7.1 mol/L HNO3 solution. 3) Moving the solution up to the column in time to avoid the disproportionating reaction of Np(Ⅴ ).

4) Washing the column with 7.1 mol/L HNO3 solution about 20 column volumes.

5) Eluting: using 3 column volumes 0.35 mol/L HNO3 and 17 column volumes 0.35 mol/L HNO3/ 0.1 mol/L N, N-dimethylhydroxylamine (DMHAN) to deoxidize and elute Pu orderly.

6) Extraction: adjusting the elution of 6) to the medium of 6 mol/L HNO3 solution, some minutes later, extracting the Pu with 0.1 mol/L TOPO/cyclohexane same volume as elution for 10 min by shaking, centrifuging 2 min. After phase separation, the organic phase is washed with 6 mol/L HNO3 solution one time, thus the organic phase is product. 7) The organic phase is transferred into a 20 mL polyethylene vial and scintillator cocktail are 194 Annual Report of China Institute of Atomic Energy 2007

added, than measure the product by liquid scintillation spectrometry. In order to validate chemical yield of the procedure, using 239Pu as tracer, the chemical yield is 95.87%. Weigh the solution 18.68 mg which is diluted HLLW of 250 times, separation and purification as the procedure, the product measured by HPGe γ spectrometry, which is closed to the background spec-trometry, so the product is radiochemical pure and has high decontamination factor for the inter- ferential nuclides such as 137Cs and so on. As a result, the α activity of Pu in HLLW is 1.03×105 Bq/g, which is tally with the value of literature.

Spectrophotometric Determination for Measuring Micro Th in Liquid Solution

YANG Jin-ling, YANG Chun-li, -de, DING You-qian, SU Shu-xin

The half life of 232Th is 1.405×1010 a. So activity of 232Th in the residual solution after electro- plating is very low. In order to get accurate data, a lot of time has to be cost for measuring. But it is unpractical for numerous samples. Then spectrophotometry is applied because of modest sensitivity and detecctability. Arsenazo Ⅲ is often used as colorimetric reagent for Th and U. In this experiment, 0.5 mL arsenazo Ⅲ of 0.1% was added to 10 mL volumetric flask. The result shows that it is enough. Acidity of the system is very important for measurement using spectrophotometry, because color development reaction and stability of the complex are dependent on acidity seriously. 1 mol/L nitric acid was usually used in reference. But we can not repeat the result in this condition. The complex is instability and its absorbency reduces obviously in 10 min. 0.4 mol/L chloroactic acid-sodium chloroacetate buffer solution was applied to solve this problem. The pH of the solution is about 2.7. At last reagent blank was used as reference to get the standard curve of Th. Maximum absorption wavelength is 672 nm. It is demonstrated that the curve agrees with Beer law within 7 mg/L. Detection limit and lower limit of this method are 2.93 μg/L and 9.77 μg/L, respectively.

Measurement of Gamma Ray Emission Probability of 173Lu and 174Lu

SUN Hong-qing, DING you-qian, MA Peng, CUI An-zhi, TANG Pei-jia

There is some dispute about the gamma ray emission probability of 173Lu and 174Lum, g, so we try to measure the gamma ray emission probability by experimentation again. Our work will can establish basic experimental date for measuring the gamma ray branching ratio of 173Lu and 174Lum, g well and truly.

The gamma ray emission probability ni of ith gamma ray measured by the HPGe gamma ray spectroscopy detector is defined as follows: FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 195

N λt 111 n =⋅i r ⋅ ⋅ ⋅ i −λtr −λT εitffmla1e− c e

Where Ni is the photopeak area of no. i gamma ray (count of full-energy peak); εi is the detection efficiency; tl and tr are the live time and real time, respectively; T is the time from the reference time to the acquisition time; λ is the decay constant; fc is the absorption correction factor; fa is the coincidence correction factor (fc≈1, in this work); m is the mass of the sample. The 173Lu and 174Lum, g is generated by (p, n), (p, 2n) reaction with a cascade accelerator to irradiate the naturally occurring isotope Yb. After the separation and purification, we will obtain the pure liquor of 173Lu and 174Lum, g, and then take out some liquor sample (about 60 mg) to fall in drops on the filter paper within a sample box with the material of organic glass, wait for some time until the sample is dry and pressurize the sample. We will prepare 4 same samples and measure them by an HPGe gamma ray spectroscopy detector located at 30 cm above the detector window. The calculated gamma ray emission probability of 173Lu and 174Lum, g is shown in Table 1.

Table 1 Gamma ray emission probability of 173Lu, 174Lum, g and uncertainty

－1 －1 Emission probability (ni) /(mg ·s ) Nuclide Energy/keV Relative standard uncertainty/% 1# 2# 3# 4# Average

173Lu 78.63 880.51 880.09 881.95 881.35 880.97 0.87

100.72 379.46 379.36 379.10 380.07 379.50 0.82

171.392 212.91 212.85 213.22 213.71 213.17 0.82

179.365 98.93 98.91 98.68 98.78 98.82 0.84

272.105 1 605.94 1 607.51 1 606.65 1 610.54 1 607.66 0.77

636.11 117.99 117.63 118.21 117.92 117.94 0.78

174Lug 76.468 49.99 50.56 51.40 49.91 50.47 0.91

1 241.85 32.03 32.51 32.53 32.36 32.36 0.88

174Lum 67.06 29.21 28.57 27.46 30.23 28.87 7.19

992.087 1.85 1.88 1.91 1.87 1.87 20.04

Comparison of Detection Efficiency for Four Gamma Ray Detectors

MA Peng, SUN Hong-qing, TANG Pei-jia

This work compared the detection efficiency of four gamma-ray detectors (a 3˝×3˝ NaI(Tl) scintil- lation detector, a planar high-purity germanium detector, a coaxial high-purity germanium detector with a relative efficiency of 40% and a broad energy high-purity germanium detector with a relative efficiency of 30%) throughout the energy range from 26 keV to 1 408 keV by measuring a series of point-source (241Am, 155Eu, 57Co, 133Ba, 137Cs, 54Mn, 65Zn, 22Na, 60Co, 152Eu) in laboratory. The calculated detection efficiency of gamma-ray detector system as a function of energy is shown in Fig.1. 196 Annual Report of China Institute of Atomic Energy 2007

The result indicates that the NaI(Tl) scintillation detector is widely used in the monitoring of environmental radioactivity and biomaterial’s radioactivity because of its good detection efficiency; the coaxial high-purity germanium detector applies to measuring the gamma ray in the region of energy from 100 keV to 10 MeV; the planar high-purity germanium detector fits for the measurement of low-energy gamma ray and Χ ray; the broad energy high-purity germanium detector has the merit of planar high-purity germanium detector and axial high-purity germanium detector simultaneously; it has high detection efficiency and good energy resolution for the low and high energy gamma ray, so we can complete a majority of measurement of activity in the domain of radiochemistry and nuclear chemistry by a broad energy high-purity germanium detector.

Fig. 1 Detection efficiency of gamma ray detector located at 25 cm above detector window

●—A 3˝×3˝ NaI(Tl) scintillation detector; ■—A coaxial high-purity germanium detector;

◆—A broad energy high-purity germanium detector; ▲—A planar high-purity germanium detector

Correction Method of Deviation in EDXRF

ZHENG Wei-ming, SONG You, LIU Gui-jiao, WU Ji-zong

The HOPG diffractive EDXRF is a special instrument developed by us, which can be used to determinate uranium and some fission products in HLLW directly because of usage of HOPG. The common sequence in routine analysis is firstly a standard curve is made, and then the specimen is determined everyday without making standard curve. In fact the instrument status is changing anytime, so the standard curve may deviate from the initial one, a correction method is necessary to obtain exact analysis result. In this work, two-point method was studied. When making standard curve, two of the standard specimen are took out as standardization samples named alfa sample and beta sample. In routine analysis the alfa sample and beta sample are determined before detecting pending sample, α coefficient and β coefficient are obtained through comparing the current intensity to the initial intensity of the standardization samples. Then the standard curve is corrected by the coefficients. The result shows that the RSD of slop of the standard curve obtained in different day is 4.6%, and FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 197

the value was reduced to 0.67% after correcting by the coefficients. To make the process easy a VB sub program was encoded and added into the main program. The flow chart of the program is shown in Fig. 1.

Fig. 1 Flow chart of program

Determination of Micro Silver in Plutonium Product

LIU Huan-liang, ZHANG Li-hua, FAN De-jun, SU Tao

PuO2 is dissolved with the mixed acid, which includes strong HNO3 and HF. Ag was separated from plutonium with CL-TBP resin to eliminate the interference of matrix. The concentration of micro silver is measured by ICP-AES at the wavelength of 328.0 nm. For 50 mg sample, the determination limit is 10 μg/g Pu. The relative standard deviation for sample is better than 2.0%. The recovery of the method is between 104% and 108%. The method is suitable for measuring the concentration of other ions in Pu product. 198 Annual Report of China Institute of Atomic Energy 2007

Matrix’s Influence by HOPG Pre-diffraction EDXRF

SONG You, ZHENG Wei-ming, LIU Gui-jiao, WU Ji-zong

X-ray fluorescence analysis is an important instrument analytical method, which has very broad applications. But it is rarely applied in spent fuel reprocessing process because of the interference of the instrument. According to the reference and basing on the theory of XRF, a set of HOPG Pre-diffraction EDXRF analytical system was developed in our XRF laboratory. In actual measure, the influence of the matrix elements on the determination of uranium in 1AW was researched because of the very complex matrix makeup. 1) Influence of matrix elements In the experiment, the solutions that comprise 100 mg/L U and the matrix elements of different concentration are compounded. The matrix elements’ concentration is from 50 mg/L to 3 000 mg/L. The results indicate that some elements such as Na, Fe, Al, Ru, Cs, Pd, Nd, Ce had not the remarkable influence with matrix concentration under 1 000 mg/L on the determination of uranium. But the influence of Sr, Y, Mo, Zr on the determination of uranium can not be ignored. A linear calibrations curve of the uranium ln IU vs. the concentration of Sr, Y, Mo, Zr are obtained. The experimental result is shown in Fig. 1.

Fig. 1 Calibration curves of U ln IU vs. concentration of Sr, Y, Mo, Zr

2) Influence of matrix Y vs. different concentrations of U solution The concentration of U solution is 50, 100 and 200 mg/L. And the concentration of the matrix Y is from 25 mg/L to 3 000 mg/L. The experimental result is shown in Fig. 2. 3) Correction method of matrix elements’ influence The correction method was given as the following for Sr as an example. The relations equation is ln IU＝－0.000 143 8ρSr+8.167 672 7, which the intercept physics meaning is the U ln IU lacking in the matrix Sr, namely ln IU0. The influence of Mo, Zr, Sr, Y can be corrected by the mathematic method on the relationship basis. The influence of Mo, Zr, Sr can be corrected by the scatted target-line too. But the Y correction is not perfect. The influence of Y should be more researched aftertime. The correcting result by the scatted FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 199

target-line is shown in Table 1.

Fig. 2 Calibration curves of different concentrations of matrix Y vs. different concentrations of U solution Concentration of U solution，mg/L：■—50；◆—100；▲—200

Table 1 Correcting Sr’ result by scatted target-line

－1 －1 ρSr/(mg·L ) Count rate (U Lα)/min RSD(count rate (U Lα))/% IU/IAg RSD(IU/IAg)/%

100 3 486.7 0.334

200 3 285.9 0.314

500 3 313.5 0.336 15 7.9 1 000 3 184.9 0.32

2 000 2 669.9 0.279

3 000 2 245.6 0.28

Determination of Nitrite in Nitric Acid Medium by Fluoremetry

SU Yu-lan, FU Jian-li, JIN Hua, YING Zhe-cong, WU Ji-zong

During the reprocessing of spent fuel, photolysis and radiation decomposition of nitric acid and dissolution of component can produce nitrite, and sometimes it is necessary to add nitrite for adjusting the valence state. The concentration of nitrite can affect the valence state distributing of Np, Pu and split elements. So it is necessary to analyse the concentration of nitrite in spent fuel reprocessing process. A new fluoremetric method for the determination of nitrite in nitric acid medium was studied. The compound produced by the reaction of nitrite with 5-aminofluorescein in nitric acid medium has high fluorescence in alkaline medium. So the concentration of the nitrite was determined by detecting the intensity of fluorescence of the compound when it is in alkaline medium. The study chose the excitation wavelength and the emission wavelength of the determination of nitrite by fluorospectrophotometry, and studied the stability of nitric acid solution, the impact of acidity on the diazotization reaction of 5-aminofluorescein and nitrite, the impact of time on the fluorescent intensity of the diazotization reaction of 5-aminofluorescein and nitrite, as well as the impact of concentration of NaOH on the fluorescent intensity. The precision of method is listed Table 1. 200 Annual Report of China Institute of Atomic Energy 2007

This technique is characterized with high sensitivity, easy operation and low interference. It can be used for detecting nitrite directly in spent fuel reprocessing process.

Table 1 Precision of method

－ －1 － －1 No. c(NO2 )/(mg·L ) Fluorescent intensity No. c(NO2 )/(mg·L ) Fluorescent intensity

1 0.20 1 415 4 0.20 1 500

2 0.20 1 460 5 0.20 1 155

3 0.20 1 240 6 0.20 1 370

Notes: x ＝1 356.7, RSD＝9.8%

Determination of Ag in Technique Process Research

SU Tao, ZHANG Li-hua, FAN De-jun, LIU Huan-liang

Based on the chromogenic reaction of Ag with p-dimethylamino benzyl rhodanmine, a new spectrophotometric method for determination of Ag in the presence of PVA-124 and Triton X-100 as surfactant is established. The factors such as acidty, reaction time and the concentration of surfactant were studied. The results show that the appropriate conditions are as followings: the concentrations of p-dimethylamino benzyl rhodanmine, PVA and Triton X-100 are 0.1 g/L, 10 g/L and 0.16% respectively; acidity is 1.0 mol·L－1; reaction time is 20 min; adsorption wavelength is 470 nm. The influence of several coexisting ions, especially Pu(Ⅳ ) on analyzing Ag was also studied. The results indicate that when the concentration of Ag is less than five times of the concentration of Pu, PMBP is used to extract Pu(Ⅳ ). The optimum extraction conditions are as follows: the concentration of PMBP is 0.1 mol/L; acidity is 2.0 mol/L; the ratio of organic and water phase is 1﹕1; Extraction time is 3 min. Conformity to Berr’s law was obtained with the scope of 0.1-1.0 mg/L. The determination limit of Ag is 0.1 mg·L－1. The relative standard deviation for this method is 2.6% (n=3). The recovery is 104%-114%.

Determination of Alpha Nuclide Activity in Organic Samples With Activity

LIANG Liang, LIU Quan-wei, LUO Zhong-yan

Components of the analytic samples with activity are complicated. Some of the samples are brown organic liquid, and the others are pink inorganic liquid which mixed with little organism. A same procedure for determination of alpha nuclide activity in the samples with radioactivity is provided for all of the samples. Since the creeping property of organism on heating, the organic samples for alpha counting can not be directly prepared by simple heating evaporation. In this work some organic components in the samples was safely removed by distillation without FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 201

loss of alpha activity. The residual organism was then carbonized by concentrated H2SO4 and thoroughly digested with HNO3-HClO4 mixture. Plutonium was separated from other alpha emitters by anion exchange chromatography after oxidation state adjustment and quantified by a large area grid ionization chamber alpha spectrometer. The alpha activities of other nuclides were measured in a similar way, but without chromatographic separation. In this case a correction for self-absorption has to be performed. The self- absorption coefficient was obtained by comparison of 239, 240Pu activities measured with and without chromatographic separation for the same sample. The good agreement was obtained through proficiency test using the above sample preparation and measurement method.

Determination of Anions in Ammonium Biuranate by Ion Chromatograph

DENG Wei-qin, TAN Shu-ping, YANG Xiao-mei, MA Gui-lan

Ammonium biuranate is an important intermediate product of the uranium mineral purification process. The smelting process of uranium mineral is complex as an important raw material for nuclear fuel cycle. The contents of impurities in ammonium biuranate are strictly controlled. So it is necessary to determine the impurities. The ion chromatograph method for determination of anion was established in ammonium biuranate. EP-SA-4A anion column and AMMS-11 anion suppresser were used. The mixed solution of 1.8 mmol/L

Na2CO3 and 1.7 mmol/L NaHCO3 was used for elution with the speed of 0.5 mL/min. The injection volume is 100 μL. In order to maintain the separation capability, after determination, 1 mol/L HCl was used to wash the column at the speed of 1 mL/min, deionized water at the speed for 15 min, and then 0.1 mol/L NaOH solution at the speed of 1 mL/min. At last the deionized water was used to wash the column to neutrality.

The sample was digested with HClO4 as the solvent. The ion chromatograph was used to determine － － 2－ 3－ F , Cl , SO4 , PO4 in ammonium biuranate. The results are accurate and reliable compared with other laboratories.

Determination of Mo, Fe, Th, Ti in Uranium Compound by ICP-AES

SU Yu-lan, QIAO Ya-hua, ZHAO Li-fei, SONG You, TIAO Miao-miao, YING Zhe-cong, KANG Hai-ying

Department of Science, Technology and International Cooperation of China National Corporation organizes some of the subsidary companies for a regular test of uranium compound componential analysis on the management ability of radiation dose and the quality of metrical data. This is initiated for the purpose of maintaining the consistency and source-tracing tradition in chemical measurement in nuclear industry and strengthening the monitoring and standardised management in uranium compound laboratories. 202 Annual Report of China Institute of Atomic Energy 2007

The extraction chromatography-ICP/AES was used to determine the elements of Mo, Fe, Th, Ti in uranium compound. The CL-TBP levextrel resin was used as stationary phase. Mo, Fe, Ti are separated by HNO3 as the mobile phase. And Th is separated by HCl solution as mobile phase. The elements separated from the compound are determined by ICP/AES. With the method we analyzed the unknown componential uranium compound which was dispensed in the nuclear industry to validate analytical ability in 2007, the data obtained were around the median compared with other laboratories’ results, and the analysis results obtained were all satisfactory. The results are listed Table 1-4. In Table1-4, the units code L19 is Chemical Analysis and Test Center of China Atomic Energy Institute.

Table 1 Measuring result of Mo in sample Table 2 Measuring result of Fe in sample

Units Mo content/(µg·g－1) Criterion Z ration Units Fe content/(µg·g－1) Criterion Z ration

code AV Median IQR fraction code AV Median IQR fraction

L20 181.8 276.7 29.65 －3.20 L20 99.98 147.1 23.0 －2.05

L14 240.3 －1.22 L9 123.8 －1.01

L18 256.7 －0.67 L18 126.9 －0.88

L17 265 －0.39 L17 134 －0.57

L19 269 －0.26 L11 141.3 －0.25

L9 275.5 －0.04 L15 147 0.00

L16 278 0.04 L19 152.7 0.24

L13 279 0.08 L10 154.1 0.30

L11 294.5 0.6 L14 156.27 0.40

L15 310 1.12 L16 170 1.00

L10 323.3 1.57 L13 172 1.08

L12 336.6 2.02 L12 199.22 2.27

Table 3 Measuring result of Ti in sample Table 4 Measuring result of Th in sample

－ － Units Ti content/(µg·g 1) Criterion Z ration Units Th content/(µg·g 1) Criterion Z ration

code AV Median IQR fraction code AV Median IQR fraction

L20 98.93 141.0 15.94 －2.64 L20 2.35 7.12 1.73 －2.76

L18 133.8 －0.45 L9 5.50 －0.93

L17 135 －0.38 L13 5.78 －0.77

L9 135.5 －0.35 L16 6.42 －0.40

L11 138 －0.19 L19 6.5 －0.36

L16 140 －0.06 L15 7.12 －0.00

L19 142 0.06 L11 7.34 0.13

L15 149 0.50 L17 7.5 0.22

L10 156 0.94 L10 7.6 0.28

L13 162 1.32 L14 8.48 1..79

L14 170.89 1.88 L18 9.2 1.20

L12 191.43 3.16 L12 10.25 1.81

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 203

Development of On-Line Micro-analyzer for Hydrogen Fluoride in Uranium Hexafluoride

FAN De-jun, XIAO Guo-ping, WU Ji-zong, ZHANG Li-hua, ZHANG Huai-li

The purity is higher and the gaseous impurity of UF6 production as an important nuclear material is strictly controlled. Herewith it is very important to detect the content of HF for purifying UF6. The analyzer for HF was established. It is designed with some new techniques as the following. 1) The method of infrared photometry was used for on-line analyzing HF. In near infrared area, 2.45 μm was selected as characteristic-absorbing wavelength of HF. 2.20 μm was selected as reference absorbing wavelength of HF. 2) Double time-resolved photon beams and single geometric photon beam was used to decrease instability of light source. 3) The gas cell was designed with the technique of multi-reflection. The photon distance of gas cell is 174 cm, which decreases the determination limit of HF. 4) The decontamination set of water vapor was used to eliminate disturbance of water vapor in the air. 5) The thermostat decreases the influence of environmental temperature. 6) The part of photoelectric seclusion eliminates the disturbance of electric signal each other. 7) The card of data collection with 32 channels collects the signals of temperature and pressure at one time. 8) The software of analyzer V1.0 was designed with simple operation procedure and profuse function. The performance of analyzer is excellent as the following. The detection range is 0-1 000 Pa, the range of signal is 0-10 000 mV, the precision is 0.2%-10.2%, and the determination limit is 10.5 Pa. The excursion of zero is 10% in vacuum state within 18 h. The excursion of HF of 200 Pa is 1% within 15 h.

Development on Special Analytical System for Determination of Free Acid

ZHANG Li-hua, LIU Huan-liang, FAN De-jun, SU Tao

The determination of free-acid plays an important role in process control and analysis of spent fuel reprocessing. It is necessary to study and develop a special fast analytical system for determination of free acid. The special analytical system is particularly applicable to determination of free acid in high-level radioactive environment, which is composed of an optical fiber spectrophotometer and an automatic sample-in device. Small sample-in volume needed, fast procedure, easy operation and physical protection are its advantages. All kinds of performance and parameters satisfy the requirements of spent fuel reprocessing control analysis. For long-distance determination, the optical fiber spectrophotometer is connected with a 4.5 meters long optical fiber. In order to resolve the change of 0.1 mol/L acidity, the 204 Annual Report of China Institute of Atomic Energy 2007 measuring optical path is 2 cm. Mass of 10-20 μm in diameter optical fibers are assembled. The optical fiber probe is composed of a reflecting mirror and a concave mirror on the top of optical fibers. In order to eliminate the interference of external light, a stainless steel measuring chamber is used. The automatic sample-in device is composed of state valve, quantifying pump and pipe. The sample-in precision of 15 and 35 μL quantifying loops is better than 0.5%. The special analytical system takes less than 7 min to complete one measurement. The linear range is 0.5-3.5 mol/L. The relative standard deviation is better than 2.0% when the concentration of the free acid is about 2.0 mol/L. For samples in different medium, the results are comparable with the method of pH titration of determining the free acid in spent fuel reprocessing process.

Primary Study on Pretreatment Technology for Analysis of High-Level Radioactive Samples

SHENG Feng, TAN Shu-ping, DENG Wei-qing, YANG Xiao-mei, ZHAO Li-fei

In the analysis of spent fuel, it’s necessary to pretreat the high-level radioactive samples. 90Sr, 137Cs, and 90Y should be removed to reduce radioactive harm. The extraction chromatography is always used as pretreatment method in radiochemical quantitative analysis for its excellent extraction efficiency in radioactive experiments. Some extractants such as TBP, CMP and CMPO have high distribution ratios for uranium (VI) and low distribution ratios for strontium, cesium and yttrium. Herewith the above extractants can be used to separate strontium, cesium and yttrium from uranium.

In this study, strontium and cesium were separated from uranium solution in by using TBP-SiO2/p,

CMP-SiO2/p and CMPO-SiO2/p extraction chromatography. The distribution coefficients were determined, and the effects of acidity and vibration-time upon the distribution ratio were also studied. The recovery ratio of uranium and the separation ratios of strontium, cesium and yttrium were determined. The result shows that TBP-SiO2/p has good extraction kinetics in both static and dynamic experiments and has good separation effect to meet the requirement of the pretreatment for analytic samples.

Brief Report of Uranium Compound Proficiency Test by Chemical Analysis and Test Center of CIAE

LIU Quan-wei, SU Yu-lan, ZHENG Wei-ming

Uranium compound proficiency test was organized by Department of Science, Technology & International Cooperation of CNNC (China National Nuclear Corporation) not only for ensuring the chemical analysis and test laboratory accurate analysis results, but also for ensuring the results’ consistency and traceability in 2007. Twenty three chemical analysis and test laboratories belonging to twenty enterprises participated in this proficiency test including Chemical Analysis and Test Center of CIAE (China Institute of Atomic Energy). Seventeen analysis results for diuranate and uranium oxide were achieved by Chemical Analysis and Test Center of CIAE according to the relative requirement of FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 205

CNNC. The total results of twenty three laboratories was evaluated by the Department of Science, Technology & International Cooperation of CNNC in term of GB/T 15483-1999 (ISO/IEC Guide 43-1997). Statistical Z was adopted for evaluating the results of each laboratory. In other words the results is satisfied if |Z|≤2, not satisfied if |Z|≥2, and deficient if 2<|Z|<3. The seventy analysis results of Chemical Analysis and Test Center of CIAE are all satisfied after evaluation without deficient or unsatisfied results (Table 1). The analysis quality control and quality assurance by the Chemical Analysis and Test Center of CIAE was inspected through this proficiency test of uranium compound. The satisfied results achieved shows that performance of laboratory accreditation is successful which includes accreditation of CNLA (China National Laboratory Accreditation), accreditation of CSTIND (Commission of Science Techno- logy and Industry for National Defense) and aptitude cognizance of metrology. At the same time the satisfied results show that the employees of Chemical Analysis and Test Center have good quality consciousness and technical competence.

Table 1 Results of analysis for Uranium compound proficiency test

Y1 Y2 U1 U2 Component － － x /% s/% x /% s/% x /% s/% x /(μg·g 1) s/(μg·g 1)

U 59.282 0.062 64.546 0.037 84.660 0.000 29

Cl－ 3.28 0.16 0.30 0.03

2－ SO4 4.57 0.07 2.03 0.05

F－ <0.05 1.15 0.02

SiO2 0.178 0.004 0.127 0.002

3－ PO4 1.06 0.02 <0.1

Mo 269.0 0.026

Fe 152.7 0.055

Th 6.50 0.020

Ti 142.0 0.030

Notes: Y1 and Y2 stand for diuranate; U1 and U2 stand for uranium oxide

Effect of Various Matrix on Measurement of Isotopic Ratio of Trace Plutonium by MC-ICP-MS

LI Li-li, CHANG Zhi-yuan, ZHAO Yong-gang, ZHANG Ji-long, WANG Tong-xing

Most of the plutonium in the environment are from nuclear test, nuclear reactor accidents and spent fuel reprocessing process. The isotopic ratio of plutonium is correlated with the source of the samples. The accurate measurement of the isotope ratios of plutonium in environmental samples is useful for evaluation of the hazard of the plutonium to the public, the history and the capability of the nuclear facilities and also more information for nuclear safeguards. The ratio of uranium to plutonium is approximately 106-107 in environmental samples and the effect of uranium and other elements on the measurement of the isotopic ratio of plutonium can not be ignored. 206 Annual Report of China Institute of Atomic Energy 2007

The study of the effect of matrix including uranium and the impurities in environmental samples on the measurement of the isotopic ratio of trace plutonium was performed by multi-collector inductively coupled plasma mass spectrometry (MC-ICP-MS). The effect of 238UH+ and the tailing of 238U at m/Z= 239 was studied by measuring a series of natural uranium solutions with different contents. The results show that the average of 238UH+/U+ is 6.0×10－4 when the content of uranium ranged from 10 pg·g－1 to 2 ng·g－1, and the effect of uranium on the measurement of isotopic ratio of 5 pg·g－1 plutonium is significant when the content of uranium is higher than 1 ng·g－1. The influence of metal ions on the determination of plutonium isotopic ratio has been also studied by fractional factorial designs. The results show that Na, K, Mg, Ca, Al, Fe at 10－6 level have no effect on the determination of plutonium isotopic ratio, but the influence of thorium is significant even at 10－7 level.

Measurement of Isotopic Ratio of Trace Plutonium by MC-ICP-MS With Dynamic Mode

ZHANG Ji-long, WANG Tong-xing, CHANG Zhi-yuan, LI Li-li, ZHAO Yong-gang

The isotope composition of plutonium is correlated with the grade and origin of the plutonium. So, precise and accurate determination of isotopic ratio of plutonium in environmental samples can assist to identify the origin of plutonium, even to uncover the clandestine nuclear activities. The content of plutonium in environmental samples is too low to be received by faraday cups when determined by MC-ICP-MS. Ion-counting detectors are available for the low ion counts except for the unknown different coefficient between the detectors. So the difference between the detectors and the mass bias became the main factors which affect the results. In order to use the 242Pu/239Pu isotope standard material to calibrate the mass bias, as well as to eliminate the different coefficient between the detectors, a new method, multi-dynamic method, was adopted to measure the plutonium isotopic ratio by MC-ICP-MS. With spiked sample was introduced, four ion-counting detectors were used to receive the plutonium ion beams. Different ion beams were counted at three measurement sequences, which were listed in the Table 1. The 240Pu/239Pu in the sample was calculated using the following equation. The mass bias and the different coefficient of the detectors could be calibrated simultaneously by this method.

⎛ 239 ⎞ ⎛ 239 ⎞ ⎛ 239 ⎞ ⎛ 239 ⎞ ⎛ 239 ⎞ ⎛ 239 ⎞ ⎜ ⎟ = 3 ⎜ ⎟ ⎜ ⎟ ⎜ ⎟ ⎜ ⎟ /⎜ ⎟ ⎝ 240 ⎠cal ⎝ 240 ⎠1⎝ 240 ⎠2 ⎝ 240 ⎠3⎝ 242 ⎠cal ⎝ 242 ⎠3

The relative standard deviation is better than 0.5% when 5 pg·g－1 level plutonium is measured.

Table 1 Measurement sequence for multi-dynamic method

Sequence Ion-counting detector L3 Ion-counting detector L4 Ion-counting detector L5 Ion-counting detector L6

1 240Pu 239Pu

2 240Pu 239Pu

3 242Pu 240Pu 239Pu FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiochemistry and Nuclear Chemistry 207

Determination of Plutonium in Environmental Samples by ID-MC-ICPMS

ZHU Liu-chao, WANG Tong-xing, ZHAO Yong-gang, ZHANG Ji-long

A method for determination of trace plutonium in environmental samples by ID-ICPMS was established in the laboratory. The content of plutonium in an IAEA conference material IAEA-368 was determined by the method. Sextuple samples and the 242Pu spike were weighed into crucibles. After ashing at 600 ℃ , the samples were leached by nitric acid. Plutonium in the leaching solution was separated and purified by TBP and TOA extraction chromatographic column. The operating parameters of the MC-ICPMS were optimized by using a 10 pg·g－1 Pu solution. The mass bias was corrected by plutonium isotope standard solution. The determined concentration of plutonium in IAEA-368 is (12.74±0.51) pg·g－1, which agreed well with the value deduced from the reference value.

Inter Comparison on Isotopic Abundance Measurement of Neodymium

JIANG Xiao-yan, ZHAO Yong-gang, LI Li-li, ZHANG Ji-long, WANG Tong-xing

The consistency between the experimental results and the reference value are indicated by repeatability and reproducibility. The inter comparison measurements are often adopted to evaluate the repeatability and reproducibility. The purpose of inter comparative experiments is to validate the experimental results coming from the laboratories which have joined the experiments and to evaluate the ability and the level of the various laboratories. An inter comparison on isotopic abundance measurements of neodymium had been performed by MC-ICP-MS. The operating parameters for determining the abundance ratio of Nd by MC-ICP-MS were studied and optimized by Nd reference material. Faraday cups were used to receive the signals of seven isotopes of Nd. The mass bias and K factor had been calculated and emendated by measuring the isotopic ratio of 142Nd/144Nd, 143Nd/144Nd, 145Nd/144Nd, 146Nd/144Nd, 148Nd/144Nd, 150Nd/144Nd in Nd reference material. The isotopic ratio of Nd in samples had been calibrated by K factor and the final isotope abundance of Nd in samples had been obtained. The uncertainty of the results had been evaluated and listed in the Table 1. The results showed the high precision and the satisfied repeatability.

Table 1 Results of abundance of Nd isotope

Isotope Isotope abundance Expand uncertainty (K=2) Isotope Isotope abundance Expand uncertainty (K=2)

142Nd 0.256 35 0.000 19 146Nd 0.162 50 0.000 11

143Nd 0.115 101 0.000 073 148Nd 0.054 332 0.000 058

144Nd 0.279 93 0.000 14 150Nd 0.053 157 0.000 076

145Nd 0.078 633 0.000 050 208 Annual Report of China Institute of Atomic Energy 2007

Calculation of Full Energy Peak Efficiency and Coincidence-Summing Correction Using Monte-Carlo Method for Measuring Disk Source by HPGe γ-Spectrometry

LI Jian-hua, FENG Shu-qiang, XU Shu-yan, LI Li-li, CHANG Zhi-yuan

A computer code based on EGS4 Monte-Carlo simulation system for calculating full energy peak efficiency and coincidence-summing correction when disk source was measured by HPGe detector was developed. The code could be used in activity measurement of environmental filter and swipe samples when the standard sources in the defined geometry were unavailable. The primary physical model was set up with the given parameters of the commercial HPGe detector. The model was further modified by revising the parameters such as the thickness of dead layer and length of inner hole which were determined by measuring the standard source. After the PEGS input card was filled, the code including the main program, geometrical transport process and record output process was compiled and the calculation by Monte-Carlo method was carried out. A unique means was confirmed in order to make the position of the samples more representatives during the modification of the physical model. At first, a helix line, starting from the center of the surface of the detector and end at the opposite boundary of the sample chamber, was made. Then the sample chamber was divided equally into six parts according to the axis position, the radial position and the angle by seven points on the helix line. The full energy peak and the coincidence-summing correction were determined using 137Cs and 60Co standard sources with the diameter of 3 mm. For the full energy peak efficiency of 662 keV γ-ray of 137Cs disk source, the bias between the values of measurement and calculation is less than 2.0%. For the coincidence -summing correction of the 1 173 keV and 1 332 keV γ-rays of 60Co disk source, the bias is within 3.0%. The results calculated by Monte-Carlo method agree well with the determined ones. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radioactive Waste Treatment and Disposal 209

Radioactive Waste Treatment and Disposal

Characterization of Polar Component of Adsorption Energy by Inverse Chromatography

ZHANG Zhen-tao, GAN Xue-ying, YUAN Wen-yi, WANG Lei, XING Hai-qing

The surface property of glass fissure can be described by the polar component of the adsorption energy which can be characterized with the inverse gas chromatography. d The coherent work of the solid surface Wa is the sum of dispersive and polar work per unit area Wa sp and Wa . d sp Wa＝Wa +Wa (1) When the glass powder is filled in the column of the chromatography and the polar probe is injected into the column, equation (1) can be changed into equation (2). d sp －ΔG°＝NaWa +NaWa (2) Where N is constant of Avogadro; a is area of the probe molecule on the glass surface. Equation (2) can be changed into equation (3). －ref sp －ΔG°＝－ΔG° +NaWa (3) where －ΔG°－ref is the adsorption free energy of assumed alcane with the molecule topological number sp equal to that of the polar probe. The polar component γs is determined by equation (4). sp sp －ref γs ＝Wa ＝－(ΔG°－ΔG° )/Na (4) Chloroform is selected as the polar probe and the non-poar probes are methane, heptane, octane, nonane and decane. The probes are injected by the Hamilton Constant Rate Syringe (CR-700-20) into the column filled by 11.0 g of glass immersed in Beishan underground water at 150 ℃ for 14 d. The carrier media is helium with the flow rate of 25 mL/min. The column temperature is 100 ℃. The polar sp 2 component of glass surface γs is 233 mJ/m .

Measurement of Fissure Surface Area Inside Glass Block by Inverse Chromatography

ZHANG Zhen-tao, GAN Xue-ying, YUAN Wen-yi, WANG Lei, XING Hai-qing

The surface area of the fissure inside the glass block is an important parameter influencing the long term behavior of high level radioactive waste glass in the aqueous media during the deep geological disposal. Inverse gas chromatography is used to study the surface area and specific surface area of these fissures. The fissure webs inside the glass block are simulated by the voids between the glass particles filled in the column of the chromatography. The diameter of the glass particle is between 80 and 100 meshes and the glass particles were immersed in Beishan underground water with water to glass mass ration of 210 Annual Report of China Institute of Atomic Energy 2007

40 to 15 at 150 ℃ for 7, 14, 28 and 90 d, respectively. After immersion, the glass samples were filtered and dried at 120 ℃ for 3 h. 11 g glass samples were filled in the column with a diameter of 6 mm and a length of 600 mm. The column temperature was kept at 50 ℃ with the temperature of the injection and chamber at 200 ℃ . The carrier media is helium with a flowrate at 25 mL/min. The probes injected were methane and the pentanol. The peak of the methane is used to determine the dead volume of the column and the peak of methane is used to calculate the adsorption isotherm of the pentanol onto the glass surface. According to the method of elution of characteristic points, each point at diffuse side of the peak of the pentanol corresponds to each point on the isotherm curve with the height of the chromatogram proportion to the pressure of the pentanol and the retention time proportion to the first derive of the isotherm as described in Fig. 1. The isotherm is related with the chromatogram by the following equation: ⎛ ∂N ⎞ 1 D ⎜ ⎟ ＝ ⋅ c (t －t ） (1) ⎜ ∂p ⎟ RT m R 0 ⎝ ⎠L,tR Where N is the adsorption amounts of pentanol on the surface of the glass; p is the pressure of pentanol; tR and t0 are the rentention time of pentanol and methane, respectively; m is the mass filled in the column of the chromatography. After the adsorption isotherm is calculated, the monolayer capacity of pentanol adsorbed on the glass surface will be determined and the surface area of the glass will be obtained. The study showed that inverse gas chromatography technique is practical and precise for the measurement of the fissure areas inside the glass block. The relative standard deviation for the surface area is less than 10% as listed in Table 1.

Fig. 1 Determination of isotherm from chromatogram

Table 1 Fissure surface areas measured by IGC

Immersion days/d S/(m2·g－1) Relative standard deviation/%

7 0.283 6.1

14 0.320 6.0

28 0.389 9.0

90 0.514 6.2 FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radioactive Waste Treatment and Disposal 211

Determination of Optimum Parameters of Inverse Gas Chromatography

ZHANG Zhen-tao, YUAN Wen-yi, GAN Xue-ying, WANG Lei, SHI He-ping

The alteration amounts of glass and the longevity of the metal package are two important parameters for the assessment of the disposal repository of the high-level radioactive waste glass. Inverse gas chromatography is used for the characterization of the surface properties of solid materials by measuring the surface physic-chemical parameters. By the curve of surface parameters versus time, the alteration amount of the glass and the longevity of the metal packages will be predicted. In order to measure the surface physic-chemical parameters precisely, it is necessary to run the inverse gas chromatographer in optimum parameter. Using glass and copper powder as the filling solid in the column of the chromatography, the optimum parameters were obtained and the analytical deviation was evaluated. The probes will be the alcanes with the carbon atoms from 6 to 9 in one molecule (C6-C9) or the n-alcanes with the carbon atoms 7 to 10 in one molecule (C7-C10). The temperatures of the column will be 40 ℃ for the probes of the n-alkenes C6 to C9 or 50 ℃ for the probes of the n-alkenes C7 to C10. The filling amounts in the column will be 18 g and the flow rate of the carrier gas will be 20-40 mL/min. The analytical relative standard deviation will be less than 3%.

Solubility of Technetium (Ⅳ ) in Beishan Groundwater

WANG Bo, LIU De-jun, YAO Jun, LONG Hao-qi, GUAN Hong-zhi, SONG Zhi-xin, ZENG Ji-shu, SU Xi-guang, FAN Xian-hua

The Beishan region is the potential high-level nuclear waste disposal site in China and the investigation of technetium (Ⅳ ) solubility in groundwater from the Beishan region was performed. The solubility of Tc(Ⅳ ) was measured under the anaerobic condition in an argon atmosphere with an oxygen content of less than 5×10－6 and using stannous ions to maintain the reducing condition. All experiments were performed independently from oversaturation and undersaturation directions to demonstrate the steady state were reached. Ultrafiltration method (10 000 molecular weight cut-off) was used for the separation of liquid and solid, and the solvent extraction method was used to separation of Tc(Ⅳ ) and Tc(ⅦⅣ ). The concentrations of Tc( ) were measured with liquid scintillation counter. Similar solubility values of Tc(Ⅳ ) were obtained from oversaturation and undersaturation directions, which indicate that the steady-state were reached within 25 d. The solubility of Tc(Ⅳ ) (as defined here by filtration through 10 000 molecular weight cut-off) is in the range of 2-4 nmol/L. The results of the experiments indicate that pH value has no significant effect on the concentrations of Tc(Ⅳ ) in the pH range from 5 to 9. The concentrations of Tc(Ⅳ ) are independent of the 2－ －4 －2 concentrations of CO3 in the range of carbonate concentrations from 5×10 to 1×10 mol/L, both in redistilled water and simulated groundwater. The TcO(OH)2 may be the main controlling phases of Tc(Ⅳ ) solubility. 212 Annual Report of China Institute of Atomic Energy 2007

These data could help to understand the chemical behaviors of Tc(Ⅳ ) in Beishan groundwater under reducing conditions, and provide parameters for the safety assessment of the candidate high-level radioactive waste disposal repository in Beishan region of Province, China.

Research on Diffusion of 99Tc in Bentonite

SONG Zhi-xin, YAO Jun, SU Xi-guang, LONG Hao-qi, WANG Bo, GUAN Hong-zhi, CHEN Xi

The research on the radionuclide migration behavior is an extremely essential question for the high-level radioactive waste disposal. 99Tc, as a long-lived fission product, is one of the main components of high-level radioactive waste. Because of its toxicity and long-life, it is always the key point in the research, and what is more, it occupies an important position in the geological disposal of the high level radioactive waste in the evaluation of safety and environment. The diffusion of 99Tc was studied under aerobic and anoxic conditions. Under the aerobic and anoxic conditions, the diffusion coefficients of 99Tc in bentonite are 1.64×10－9 and 6.07×10－10 m2/s, respectively; under the aerobic and anoxic conditions, the coefficients of 99Tc in bentonite added sands are 3.64×10－9 and 7.00×10－10 m2/s, respectively; under the aerobic conditions, the coefficients of 99Tc in bentonite added FeO is 5.91×10－11 m2/s. The results show that the migration of 99Tc under aerobic conditions in bentonite is faster than that under anoxic conditions; and it’s faster in the bentonite mixed with sands than in the pure bentonite; what’s more, the diffusion coefficient will decrease while adding Fe into the bentonite.

Calculation on Distribution of Americium Species in Beishan Groundwater

GUAN Hong-zhi, ZHANG Zhen-tao, SU Xi-guang, LONG Hao-qi, WANG Bo, YAO Jun, SONG Zhi-xin, CHEN Xi

Americium has lots of species in aquatic solution. It is difficult to measure the distribution of americium species directly while their species can be calculated by some programs depend on lots of thermodynamic data. The distribution of americium species in Beishan groundwater was calculated by EQ3NR for further understanding its sorption and migration behavior. EQ3NR is a part of EQ3/6 and it is used to calculate the species distribution of some nuclides and saturated index of minerals usually. EQ3/6 is a powerful geochemical modeling code and it was developed by Lawrence National Laboratory for HLW deposition of Yucca Mountain. The distribution of americium species in Beishan groundwater was calculated at 25 ℃ , assuming that the total concentration of americium is 10－11 mol/L. When pH value is in the range of 4-6, the main + 3+ － species of americium is AmSO4 , about 50%, and the proportions of Am and Am(SO4)2 are more + than 15%, respectively. When pH value is in the range of 6-8, the proportion of AmCO3 increases with － pH and has a maximum, then it decreases with pH because of the formation of Am(CO3)2 , and other 2－ species of Am get fewer and fewer. When pH value is higher than 8, the most Am complex with CO3 FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radioactive Waste Treatment and Disposal 213

－ and the proportion of Am(CO3)2 gets about 80%. The Eh values of groundwater have little influence on the Americium species distribution when pH value is between 7 and 9, and the influence of Eh gets weaker with the increasing of pH. This is because Am has a steady oxidation state Am(Ⅲ ) in solution. + － + 2+ When pH is between 7-8, the main species of Am are AmCO3 , Am(CO3)2 , AmSO4 , AmOH , 3+ － Am and Am(SO4)2 , and their proportion are 62.02%, 13.12%, 9.72%, 5.33%, 3.84% and 3.39%, respectively when pH value is 7.56, the actual pH value of Beishan groundwater. Some minerals such as granite get along with groundwater for a long time will form negatively-charged functional group on its surface. This is in favor of the sorption of Am on minerals; hence minerals such as granite could retard the migration of Am in geological environment. The results of calculations show that the distribution of Am species can be simulated well by EQ3NR. This is in favor of studying its aquatic solution chemistry, sorption and migration behavior.

Influence of Waste Glass Composition on Solubility of Sulfate During Vitrification of HLW

LIU Li-jun, ZHOU Hui, QIE Dong-sheng, LI Bao-jun, LI Yang, XU Jian-hua, JIANG Yao-zhong

Borosilicate matrices are widely accepted as containment of high-level wastes on account of its good chemical durability and endurable formation temperatures. However, the soluble yellow second phase (yellow phase) will be produced during melting if the high-level liquide wastes contain high amount sulfate. The analysis results show that the yellow phase is a mixture of many salt crystals and is often enriched in cesium and strontium. Once disposed in deep geologic repository the vitrification form is eroded by the groundwater, the radioactive nuclides will be released from the glass and enter the biosphere. So the yellow phase has harmful effects on the performances of vitrification form. In order to resolve the yellow phase problems, it is necessary to understand sulphur behaviors in the borosilicate waste glasses, especially the relation between sulfate solubility and glass composition. The sulfate solubility limit in the glass represents the total sulfate that the glass can accommodate and not form a layer of molten salt on the melt pool. Ferrous sulfamate used as a reducing agent in separation of plutonium from uranium in our factory is the major source of the sulfate. Avoiding the formation of yellow phase during the glass melting is an important requirement during the operating of the vitrificaton plant. Concerning the yellow phase, much work must be carried out. The focus is to study the relationship between the sulfate solubility and the glass composition. To determine the relation between the sulfate solubility and the glass composition, 32 formulations were tested. The sulfate was incorporated in the glass by adding Na2SO4 in the matrices. The experiment result shows that the relation between the glass composition parameter c(O－) (the 2－ － concentration of non-bridge oxygen) and sulfate solubility is linear c(SO4 )＝1.483 3c(O )－0.089 6 with a correlation coefficient of 0.89, and the relation between the glass composition parameter c2(O－)/ 0 2－ 2 － 0 c(O ) and sulfate solubility is logarithmic, e.g. c(SO4 )＝0.225 7ln[c (O )/c(O )]－0.372 1 with a correlation coefficient of 0.90. We also discover the relation between glass composition parameter c(O－) and ln[c2(O－)/c(O0)] is linear, c(O－)＝0.151 3ln[c2(O－)/c(O0)]－0.187 6. Therefore the two models make no difference to express the relation between the glass composition and sulfate solubility. 214 Annual Report of China Institute of Atomic Energy 2007

The developed empiric models are based on the 32 data points, which are all the crucible experiment results in the laboratory. The formulations are not limited by the viscosity at melting temperature, which needn’t be in a special range. The two empiric models can be used to expect the sulfate solubility in some designed formulations. Some formulations in the literature were selected to validate the models. The results show that the values from the empiric models and experimentally determined are consistent.

Fabrication of Glass-Ceramic for Immobilization of Radionuclides

ZHANG Zhen-tao, WANG Lei, GAN Xue-ying, XING Hai-qing, YUAN Wen-yi

With the increase of the burn-up of the nuclear fuel, the amounts of the long-lived radionuclides increase. The solubility of plutonium in glass is very limited. It is therefore necessary to develop a new technique for conditioning the long-lived radionuclides. Glass-ceramic can immobilizing high amounts plutonium in the crystal phase and can accommodate various radio nuclides in the residual glass. The fabrication of glass-ceramic is feasible through the nucleation and the growth of the crystals by control of the temperature of the parent glass melt. When large amounts of high temperature parent glass are poured into the canister, the cooling of the melt is very slow. As a result, the condition for fabrication of the glass-ceramic is guaranteed. The purpose of the study is to research on the fabrication of glass- ceramic. Glass-ceramic composition is designed according to the composition model of American glass- ceramic. Thereinto the overall Nd2O3 content is 6% which is used to simulate the actinides. The content of simulated high-level radioactive wastes is 10%. The waste is a high-level radioactive wastes simulacrum from some factory. And TiO2, ZrO2 and CaO are adding chemicals to produce zirconolite crystal phase. The composition of the parent glass is listed in Table 1.

Table 1 Composition of parent glass

wB/% Sample No. CaO TiO2 ZrO2 Nd2O3 SiO2 Waste

H713 25.47 9.30 7.43 6.00 42.44 10.00

H814 22.79 9.28 7.42 6.00 45.15 10.00

H915 20.39 9.27 7.40 6.00 47.58 10.00

H1016 17.64 9.25 7.39 6.00 50.37 10.00

H1117 12.26 9.21 7.36 6.00 55.82 10.00

The glass-ceramic is fabricated by melting of homogenous parent glass at 1 500 ℃ for 2 h followed crystallization at 810 ℃ for 1 h and the growth of the crystal phase at 1 200 ℃ for 4 h. As displayed in Fig. 1, the composition of the glass-ceramic is determined by the contents of the calcium oxide. With the increasing of the calcium content in the sample, the silicon content gradually decreased, and the composition of the glass-ceramic changes from single crystal phase of sphene to two crystal phase of zirconolite and sphene and finally to single crystal phase of zirconolite. Namely, when the content of the calcium oxide increases, there is inclined to be sphene; while when the content of the calcium oxide decreases, there is inclined to be zirconolite. This result is very important for immobi- FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radioactive Waste Treatment and Disposal 215

lization of radioactive waste, because calcium is adding material, calcium content decrease means that more waste can be immobilized.

Fig. 1 Composition of glass-ceramic

Design of High Frequency Induction Power of Cold Crucible Melter System

XU Jian-hua, ZHOU Hui, QIE Dong-sheng, LIU Li-jun, LI Bao-jun, LI Yang, JIANG Yao-zhong

The cold crucible induction melter technology is the fourth generation of the nuclear waste melting treatment technology. It has many advantages such as high work temperature, long life-span of the equipment, widest disposal area and less second waste and so on. The cold crucible melter system (CCMS) consists of five major components: the high frequency induction power system, the mechanical system, off-gas system, the cooling system and control system. The high frequency induction power system is very important because its frequency, power and other parameters will affect the whole installation operating naturally. The three objects of the research are: tracking international advanced technology, offering guarantee for our nuclear waste treatment technology and providing technology sustain for industrial application in future. The theory of high frequency induction heating is electromagnetism induction law. The equipment is a AC-DC-AC metabolic frequency equipment which is made of a radio frequency generator basically. It can supply high frequency and power. Design of high frequency induction power includes two sides: parameter design and electrocircuit design and improvement. Design of the electromagnetic induction power system followed a series of intermediate designs and calculations. First, a design-basis value of melt resistivity and magnetic permeability were selected. The resistivity values of borosilicate glasses at nominal operating tem- perature of 1 150 ℃ in our country is required between 5 Ω/cm and 7 Ω/cm. So a value of 6 Ω/cm was selected as the design basis for the CCIM prototype. The magnetic permeability is space permeability. Second, the optimal frequency was determined which was based on the permeating depth of electric current and system efficiency. Third, the electrical power was determined based on the desired melter 216 Annual Report of China Institute of Atomic Energy 2007

throughput and characters of the melt. It is determined for the cylinder melter the range of the frequency is 300-700 kHz and maximum output power is 100 kW. In theory, the electrical efficiency of the designed system is 98% and the whole system efficiency is 28.6%. The next step in our work is to design electrocircuit and choose electrical parts of the apparatus. There are two kinds of high frequency power’s commutator, in series harmonic oscillation commutator and parallel connection harmonic oscillation. They have severally their advantages and disadvantages. By comparing to the two kinds of commutator, we select in series harmonic oscillation commutator and high power MOSFET. At the same time, we design the resistor, capacitor, inductor and quick resume diode. All are based on the requirements for the CCIM. Finally, the whole enginery was designed which included overall arrangement of oscillation commutator, control on oscillation commutator, frequency track electrocircuit, control and protection electrocircuit. Overall arrangement of oscillation commutator has important effect on the whole enginery, such as it can affect the stability of whole enginery. Comparing different arrangements resulted in the selection of model of power. Overall arrangement of oscillation commutator is symme- trical to reduce loss, which guarantees whole enginery is steady. Frequency track electrocircuit selectes lock phase structure, which improves accuracy and answer speed. Frequency can be adjusted continuously. Control and protection electrocircuit consists of six parts: rectifier control, over electric current and short circuit protect, over voltage protect, over heating protect and lack phase protect. These can guarantee whole enginery runs safely and the installation is not attainted in case of error-operating or suddenness. The resulting system provides induction power of up to 100 kW. Power is adjustable via the control panel, or the computer interface, continuously over the range of 0-100 kW. The generator frequency can be reconfigured (i.e. modification of specific inductance and capacitance values) to provide at any frequency over a range of 300-700 kHz. The whole enginery efficiency is more than 85% and the system efficiency is more than 20%.

Determination of Designing Parameter of Cold Crucible

QIE Dong-sheng, ZHOU Hui, XU Jian-hua, LIU Li-jun, LI Bao-jun, LI Yang, JIANG Yao-zhong

Designing and optimizing the structure of cold crucible is one of key technologies of the cold crucible melter solidification. The focus of the technology is the optimization design of the crucible structure and electromagnetic field. In order to maximize the system efficiency, the crucible needs to have good penetrating magnetism and low eddy current loss, which will produce maximal induction whirlpool in the melt. The cold crucible melter system is constructed of metal segments that are water cooled and arranged to form a crucible. Heating efficiency of electromagnetic field is affected by three factors: the parameter of the induction power, the station of induction coil and physical characteristic of melt. Penetrating magnetism of crucible and eddy current loss depends on the number of segments. The gap between two segments can make electromagnetic field act on the material and reduce eddy current loss. MBI company in USA has experimentally determined gaping, and the result shows that it is an effective method for improving efficiency. The more number of gap can achieve the more high efficiency. But when the number of gap arrives to a certain amount, the density of magnetic force line will be saturated and increasing the number of the gap will no more improve the system efficiency, while the machining FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radioactive Waste Treatment and Disposal 217

difficulty is increased. So the principle during the crucible design is “more petal and narrow gap”. The ability of penetrating magnetism is affected by the frequency of the electromagnetism and structure of cold crucible. Following the frequency ascending, magnetic flux density descends. The downtrend is increased when the frequency is above 100 kHz. In addition, segmented structure reduces eddy current loss. Higher frequency, more effect. For high frequency magnetic field which is above 100 kHz, the number of segment is 16-20. According to the frequency range of 10-100 kHz, the number is 8-12, and the frequency under 10 kHz, the number is 4-8. Experiment results show that increasing the number of petal not only improves the ability of penetrating magnetism but also enhances the uniformity of magnetic line of force in circle. However the uniformity of magnetic line of force is reduced in axes and radial. Based on above principle and considering the characteristic of melt and machining difficulty, a cylinder cold crucible which made up of stainless steel was designed. The primary parameters are follows: inner diameter, 300 mm; effective height, 290 mm; the number of petal, 48; the distance of gap, 2 mm. The shape of petal is columniform and each eight petal forms a cooled circulation. The crucible consists of three parts: the upper manifold, the lower manifold and the cooling tubes. The lower manifold was segmented six petal, which provides supply and return lines for cooling water. The inner cavity of the upper manifold was segmented six groups. This structure guarantees the wall of the crucible was cooled equably. Material of cooling tubes is stainless steel and aluminum plastic pipe. The tie-in which is machined independently provides airproof. The designed cold crucible (diameter 300 mm) not only provides design basis for the technology target and applicability of the high frequency induction power but also accumulates experience for complex cold crucible designed in future.

Radioactive Liquid Wastes Integrated Treatment Facility Went Into Work in State

YAN Xiao, LIU Fu-guo, LIU Li-ming

The radioactive liquid waste integrated treatment facility was setted up in 2003. It mainly relies on evaporation to treat the middle-level radioactive liquid wastes, and finally it will be transform into cement solidification for perpetual disposal. The facility’s capability in evaporation is 12 ton per day, and produce 15 buckets of cement solidification per day. From the year of 2003, the facility was carried on cold-experiment and alteration, and the cold-experiment and alteration made the facility have the capability of production. In the end of 2004, we completed the hot-experiment successfully, in this experiment, we treated the waste water about 100 m3, and produced cement solidification about 40 buckets. After we completed hot-experiment successfully, we were doing preparing work actively: writing project, requisition of the admission, training of the personnel, examining and repairing of the facility. When we completed all the preparing work, the facility began to work at November of 2007, up to the end of 2007, we treated the waste water about 35 m3 and produced the cement solidification 300 buckets, this work indicate that CIAE has the capability in treating middle-level radioactive waste water, and it provides a foundation for the movement of CIAE for the future. 218 Annual Report of China Institute of Atomic Energy 2007

Isotopes

Synthesis of Intermediates of 3, 4, 3-LI-(1, 2-HOPO) for Decorporating Plutonium

SHEN Lang-tao, DENG Xin-rong

Plutonium has become an important element with the wide applications of plutonium to military and nuclear industries. However, plutonium may bring dangers to human and the environments due to its very high radiation and chemical toxicities. Chelation therapy is the optimal method of treatment for any metals overload. Chelation therapy used chelating agents to decorporate plutonium is the optimal choice of reducing radionuclide-induced risks after plutonium enters into the human body. At present, 3, 4, 3-LI-(1, 2-HOPO) is the most effective decorporating agent for plutonium. Structure of 3, 4, 3-LI-(1, 2-HOPO) is shown in Fig. 1. It contains special structure of hydroxypyridinone, which has highly selective abilities and remarkable activities in vivo. In order to prepare 3, 4, 3-LI-(1, 2-HOPO), two key intermediates were synthesized and characterized by IR and 1HNMR. The fairly good yields were available for each step. The synthesis routes in the experiment are proved to be feasible.

Fig. 1 Structure of 3, 4, 3-LI-(1, 2-HOPO)

Design of Heat Fuel Core of 238Pu Radioisotope Thermoelectric Generator

LUO Zhi-fu, HE Shun-yao, TANG Xian

For radioisotope thermoelectric generator (RTG), the 238Pu radioisotope heat unit (RHU) provides heat for thermo-electric generator to get electrical power. It is need to design the RHU to meet the safety requirement of working environment and accident situation, in the other hand, it is important to get the higher rate of heat utilization. 238 The current design is for watts RTG. The PuO2 ceramic was chosen as fuel form to meet the requirement of RHU. Heat transfer of the fuel core and RHU in the atmosphere environment was analysed, the mathematics model of heat transfer was established. The temperature was calculated and compared of the core suspended in a metal capsule with a helium and air atmosphere. The thermal conductivity of the plutonium core, filled inert gas has more effect in heat transfer than the metal capsule. The surface temperature of RHU was calculated with different geometries. FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Isotopes 219

The structure of RHU with higher surface temperature through of calculation was gotten. The difference in surface temperature is under 15 ℃, the temperature value of the fuel core is 260 ℃ higher than the surface. According to the result, the thermo-electric material can be chosen and the higher efficiency of thermo-electric generator can be got.

Design of Heat Source Capsule for 3 W Radioisotope Thermoelectric Generator

LUO Zhi-fu, CAI Ding-kan, HE Shun-yao

The Radioisotope Thermoelectric Generator (RTG) was used inside space probe because of its long service time. But the plutonium-238 used in the heat source is extremely poisonous. Therefore, the safety of the heat source is of great important under working environment and accident situation. The project studied and analyzed the application environment, such as high temperature, high internal pressure, space debris etc, and the accident circumstance, such as high external pressure, seawater corrosion, solid rocket booster (SRB) fragment impact, high altitude falling etc. The researcher established the relationship of pressure (caused by gas released from the fuel)-time, and analyzed the fabricability, the mechanical properties, the diathermancy, corroding property, the compatibility with fuel of several metallic material. Chose the inner shell material and the structural shell material, designed three types of 3 W RTG heat source capsule, analyzed the stress distribution of three-types- capsule under high internal pressure, high external pressure and high velocity impact, and evaluated the safety of the heat source under accident circumstance. The results show that based on the Alloy-1 and Alloy-10 possess good fabricability, mechanical properties, diathermancy, weldability, they were chosen as the inner shell material and the second shell material. Alloy-Z and Alloy-HC posse good mechanicibility, corrosion resistances, and were chosen as the structural shell materials. The heat source capsule of type A under the condition of room temperature and high external pressure (170 MPa) did not accord with the safety criteria because of stress concen- tration. The quality of the heat source of type B was lighter and could accord with the requirement of safety under the condition of high internal pressure, high external pressure, but it is difficult to be fabricated. So the heat source was designed for type C. When the heat source impacts the steel plate at the speed of 53 m/s from the aclinic direction, the direction of 45° angles and the vertical direction, it will be safe.

Investigation on Effects of Neutron Irradiation on Tantalum

LUO Zhi-fu, HE Shun-yao, PENG Hui

Plutonium-238 dioxide is a useful alpha source of radioisotope thermoelectric generator (RTG), but it emits some neutrons. So we performed the investigation on the effects of neutron irradiation on tantalum, which has been used as inner shell for RTG. For a given power, the quality of plutonium-238 dioxide and the neutron fluence rate over a certain period of time can be calculated. In the simulated experiment of neutron irradiation, the Am-Be neutron source with a neutron fluence rate of approximately 4×107 s－1·cm－2 was used. All test specimens are a 220 Annual Report of China Institute of Atomic Energy 2007

flat “dog-bone” configuration with a total length of 50 mm, a gauge length of 14.8 mm, and a gauge width of 3 mm. The tensile specimens were tested at 25, 300 and 600 ℃, respectively. The results indicate the irradiated and the compared specimens have little difference at this irradiation level. But as the increasing of temperature, the tensile strength of Ta is reduction while the elongation is still keep on 25%. Then we also analyzed the zone of fracture by SEM. It was demonstrated that sufficient high temperature toughness of Ta can survive the increasing high pressures of the RTG’s operating environment.

177Lu Labeled Radiopharmaceuticals for Cancer Therapy

LUO Zhi-fu, DENG Xin-rong, LI Hong-yu, XIANG Xue-qin, GUO Hong-yuan, YE Zhao-yun, LI Gui-qun, CHEN Yang

Radionuclide therapy (RNT) employing radiopharmaceuticals labeled with beta emitting radio- nuclides is promising therapeutic approach for cancer and is an important part of nuclear medicine. For this use, 177Lu is an ideal nuclide. The study of 177Lu labeled radiopharmaceuticals for cancer therapy is underway in China. The Department of Isotope of CIAE began to work on study of 177Lu-EDTMP for cancer bone pain in 2007. 177 Lu was produced by irradiating natural lutetium oxide (Lu2O3) with thermal neutron fluence rate of 2×1013 cm－2·s－1 in Swimming Pool Reactor (SPR) for different time. The nuclear reaction is 176 177 177 described as Lu(n, γ) Lu. Specific activity of prepared LuCl3 solution is 1.48 MBq/μg. In order to label 177Lu-EDTMP, the different strategies of conditions including molar ratio of EDTMP/177Lu, reaction time, pH value and temperature for labeling EDTMP with 177Lu were arranged in the experiments. The EDTMP labeling yield depends on time. When the molar ratio of EDTMP and 177Lu is chosen as 1.9:1, the labeling efficiency is 75.8% for 30 min and 95.6% for 90 min, respectively. According to the reference, two freeze-dried components were evaluated. The kit composition appears good aspect and in white pieces after lyophilizing. However, the properties will be tried in further test to ensure that it will be enabling efficient labeling with 177Lu at selected condition.

Research Progress of 124Xe Gas Target System for High Purity 123I Preparation

LUO Zhi-fu, YIN Wei, ZHANG Bao-qi, LIU Yu-ping, DENG Xue-song, LIU She-yang, LIANG Cheng-hu, ZHAO Gui-zhi

With excellent nuclear properties like half-life of 13.2 h, main photon energy of 159 keV and no β－ emitting etc., 123I is special suitable for γ-camera and SPECT measurements in nuclear medicine fields. 123 Several years ago, the TeO2 solid target was developed by an institution to produce I via the 124Te(p, 2n)123I nuclear reaction. But owing to the existence of other iodine isotope impurities e.g. 124 125 126 I(T1/2＝4.2 d), I(T1/2＝60 d) and I(T1/2＝13 d) etc. So the product could not be popularized and the production was stopped quickly. Same as the main preparation method for high purity of 123I in the world, we have now developed a gas target system, using 99.9% enriched 124Xe as the target matter and via the nuclear reactions: FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Isotopes 221

++ 124Xe(p, 2n) 123 Cs⎯⎯⎯⎯→β ,5.9min 123 Xe ⎯⎯⎯⎯⎯β , e, 2.08 h→⎯⎯⎯⎯ 123 I e, 13.2 h→ 123 Te(stable)

The abundance of 124Xe in natural Xe gas is only 0.095%, so 99.9% 124Xe is very expensive. Therefore the 124Xe gas transfer and bombarding in the target system is the key to the question. The construction of our gas target system includes 3 parts: a new 30 MeV, 100 μA of proton beam line extracted from the mid way of the beam to solid target with 75° bending by the bending magnets and focused to the gas target window by two groups of quadrupoles, the gas target system itself and the related laboratories. The former one were accomplished in May, 2007 and the latter two in Nov., 2007. After completing the assembling and testing of various individual models, the whole system came to the complete testing. Firstly, we performed the experiment of using the natural Xe gas for quantitative transfer, target loading and receiving cryogenically, and obtained good results. Secondly, we performed the target chamber pressure bearing test by adding 1 MPa He and it kept no change in 24 h. Thirdly, we performed the bombarding experiment using the 568 kPa He as target matter and the beam currents from 4 μA, to 50, 80 and 100 μA, everything was ok. Finally, we performed two batches hot experiments successfully by using 99.9% 124Xe as the target material and with the beam currents of 60 and 65 μA, and got 2.22×1010 Bq and 6.66×1010 Bq of 123I in 0.02 mol/L NaOH solution, respectively. The results (seen Table 1) of the quality control for the two batches products satisfied the target expected. It declares that the first set of 124Xe gas target system for high purity 123I production developed successfully in China. This 123I production line can offer (3.7-7.4)×1010 Bq high quality Na123I solution every day after a short time completion of it.

Table 1 Quality control results of two batches 123I products

Batch No. Radioactivity of 123I/Bq Nuclear purity of 123I 1)/％ Half life/h Main γ-ray energy/keV Radiochemical purity/％

071108 2.257×1010 99.81 13.2 159 97.5

071112 6.66×1010 99.84 13.2 159 99.6

121 121 Notes: 1) During the nuclide purity analysis, the only impurity found is I (T1/2=2.12 h), and it decayed to Te (T1/2=10.8 d, γ-ray

energy of 573 keV) totally almost in 24 h

Application of Automatic Control System in 123I Production by 124Xe Gas-Target

ZHANG Bao-qi, LIANG Cheng-hu, QIN Yuan-sheng, JIANG Hai-feng, LIU Yu-ping, LIU She-yang, ZHAO gui-zhi

123I is a cyclotron produced nuclide. In order to get 123I with high purity, the highly enriched (>99.8%) 124Xe gas-target is used and by the nuclear reaction of 124Xe(p, 2n)123Cs(β+)123Xe(e, β+)123I in the world. Because of the very expensive 124Xe gas and working in the intensive irradiation field, the system has to be controlled and viewed automatically by PLC and PC matched with self made control cabinets. The 124Xe target control system includes mainly the PLC program controller, electrical control system, graphical user interface and can be operated manually and automatically. As you can see in the following figure of 124Xe gas-target system process control, we use variety of sensors for detecting the temperatures, pressures, vacuums, water flows, beam currents and radiations etc. really for various components, so as to make the safe automatic and manual control possible by the 222 Annual Report of China Institute of Atomic Energy 2007

previous set threshold values. Concerning the safe operation of the expensive 124Xe gas, we have set some viewing check windows for the open and close of the special valves related with its transfer, and set the interlock of the target pressure, target temperature, target cooling water flow, target window cooling He pressure and temperature etc. with the beam during the target bombarding. The beam would be immediately switched off whatever one of the above parameters is beyond its threshold value. In this way, the target window will be protected from being punctured effectively, so as to keep 124Xe gas in safety.

Preparation of 125I Ladled Microspheres

ZHAO Ming-qiang, XU Shu-he

Radioembolization of liver cancer was proven to be an effective therapy in nuclear medicine. The 90Y glass microspheres were used to treat both primary and metastatic liver tumors in clinic with encouraging results. By directing radioactive microspheres directly into the hepatic artery, a concen- trated dosage of radiation can be delivered directly into the tumor bed, while conserving the normal liver tissue that surrounds the tumor. The size of the microspheres causes them to become entrapped within the tumor vasculature and retained within the tumor for radioactive therapy. This study prepares radioembolization pharmacy by labeling resin with 125I. Firstly, combine tyrosine with resin, and then label tyrosine of the microspheres by Chloramine-T. The specific activity of 125I labeled microspheres is 1.2×1010 Bq/g, this is enough for brachytherapy of live tumors. But there is a lot of nuclides physical absorbed in the resin which is unstable, it is a waste of 125I, and the specific activity is less in practice than in theory. The results of in vitro stability indicate: The radioactive microspheres prepared by chemical synthesis and labeled 125I by Chloramine-T has a high in vitro stability, with no more than 1% loading releasing from the microsphers in normal human serum in a week. The radioactive microspheres prepared by chemical synthesis and labeled 125I by Chloramine-T have potential use in radioembolization therapy, with respect to their pharmaceutical quality.

Preparation of Monoclonal Antibody Against CA125 and It’s Applications in Immunoassay

FENG Shu-yuan, HAN Shi-quan, XU Wen-ge, LI Zi-ying, JIA Juan-juan, CHEN Yong-li, LIU Yi-bing

Balb/c mice were immunized with carbohydrate antigen 125 (CA125), and a competing sandwich immunoassay was used to screen positive clone of hybridoma cell screting anti-CA125 Ab, finally one monoclonal antibody against CA125 was got successfully. Applications of the antibody in IRMA and CLIA show it is an ideal substitute of coating part in the sandwich system. We performed a normal range studies in which all healthy women had assay values less than 35 U/mL. A direct relationship exits between CLIA and IRMA with commercial kits, correlative equations are y=0.85x+11.1 (r＝0.932) in CLIA, y=0.87x－12.8 (r＝0.983) in IRMA, respectively. New antibody is stable in 37 ℃ for 2 weeks.

FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Isotopes 223

Development of Surface Plasmon Resonance Based Biosensor Immunoassay for sulfadiazine

LI Zi-ying, XU Wen-ge, LIU Yi-bing, HAN Shi-quan

The veterinary drug sulfadiazine (SD) residue fast detection in foodstuff by surface plasmon resonance (SPR) biosensor was researched. SD coupled with the carrier protein bovine serum albumin (BSA) was spotted on the biosensor. After immobilization, the antibody for SD and the standard or sample mixture was injected into flow cell, and recorded the relative response (RU) of 5 min. Antigen is coated at pH=4.2 acetate buffer, for 10 min. The LOD (limit of detection) is 0.1 μg/L with the detection scope 0.1-10 μg/L. The whole time of detection is 5 min. The chip is regenerated by 0.1 mol/L NaOH solution, for 1.5 min.

Synthesis and Preliminary Evaluation of Novel Iodinated Sigma2 Receptor Ligand

FAN Cai-yun, LUO Zhi-fu

Sigma receptors are over expressed in many human tumors, such as brain tumor, sarcoma, small and non-small cell hung carcinoma, melanoma, breast cancer, and prostate cancer. Especially Sigma2 receptors in various tumors might serve as a better biomarker of their proliferative status. Thus, radiolabeled probes with a high affinity and high selectivity for Sigma2 receptors may be useful as tumor imaging agents. A novel iodinated Sigma2 receptor ligand ([125I] 1) (Fig. 1) was designed and synthesized. The labeling yield of [125I] 1 is over 90% and the radiochemical purity of is greater than 95% after extracted with dichloromethane. The ligand is stable up to 2 weeks stored in a fridge. The biodistribution studies in normal mice (Table 1) shows that [125I] 1 accumulates in sigma receptor expressing organs such as brain, heart, liver, lung, kidney and spleen, and cleared away fast. And high radioactivity was found in

Fig. 1 Structure of [125I] 1 intestine and excretion.

Table 1 Bioditribution of [125I] 1 in normal mice

Bioditribution of [125I]（x±S.D.，n=5）/(%ID·g－1) Organ 2 min 30 min 60 min 120 min blood 5±0.43 0.62±0.25 0.8±0.10 0.48±0.08 brain 2.56±0.53 0.13±0.04 0.18±0.08 0.04±0.01 heart 7.69±3.02 0.43±0.22 0.38±0.23 0.32±0.19 liver 20.22±3.98 7.35±5.19 7.35±2.94 5.14±0.89 lung 8.75±1.20 1.53±0.55 0.88±0.18 0.63±0.07 kidney 11.61±2.56 2.77±0.99 0.9±0.18 0.99±0.35 spleen 2.41±0.27 0.5±0.14 0.88±0.47 0.35±0.20 muscle 3.36±0.95 0.34±0.09 0.32±0.08 0.31±0.24

224 Annual Report of China Institute of Atomic Energy 2007

Applied Mathematics and Computer Technology

Application of Monte-Carlo Method in Monochromator Radiation Protection

LIU Bao-jie

The Monte Carlo Method was used in the design of monochromator shield in CARR, to insure the total annual dose equivalent below the vocational dose equivalent limit (20 mSv/a). The neutron and γ ray dose equivalent rates were calculated by using MCNP software package. Because of the complexity of the geometry, the reflecting surface was built during the calculation to simplify it. Geometry splitting with Russian roulette was used to reduce the calculating relative error and prove the calculating efficiency by setting the geometry in the form of a set of layers artificially. Based on the calculated results above, the total dose equivalent in different places was obtained when the shieldings were in different thickness. It is an important theoretical foundation for the shield design and radiation protection.

Monte-Carlo Calculations of Detection Efficiency and Coincidence Summing Correction for HPGe γ Spectrum Instrument

FENG Shu-qiang

The Monte Carlo method was used in the article to calculate the detection efficiency and coincidence summing correction by EGS4, which need to provide user codes. To make the physical model close to the practical instance, we make several improvements for the program. 1) Increase one region in the model as sample salver. 2) Add off-axis parameters in the model for different sample position calculations. 3) Add geometry shape choices for the sample model, cylinder or cube. To validate the correctness of the program, the detection efficiency for 137Cs and coincidence summing correction for 60Co were calculated and measured when the sample was in different position. The energy spectrum for 137Cs calculated by the Monte-Carlo is shown in Fig. 1. The detection efficiency is listed in Table 1.

Table 1 Detection efficiency

No. Position(x, y, z) Monte Carlo Experiment 1 (0 mm, 0 mm, 0 mm) 0.063 9 0.063 3 2 (5.5 mm, 0 mm, 10 mm) 0.045 9 0.046 3 3 (11.5 mm, 0 mm, 20 mm) 0.033 6 0.033 0 4 (16.5 mm, 0 mm, 33 mm) 0.024 1 0.025 2 5 (21.5 mm, 0 mm, 41 mm) 0.019 1 0.020 2 6 (26.5 mm, 0 mm, 50 mm) 0.015 5 0.015 9 7 (31.5 mm, 0 mm, 60 mm) 0.012 5 0.012 3 FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Applied Mathematics and Computer Technology 225

The results calculated by the Monte-Carlo method and measured by using gamma spectrum instrument agree very well. The relative differences of calculated and actually measured coincidence summing corrections are within 5% and 10%, respectively.

Fig. 1 Energy spectrum for 137Cs

Effects of Accelerating Growth on Evolution of Large Harmonious Unifying Network Model*

LI Yong, FANG Jin-qing, LIU Qiang

So far, our group has proposed and investigated three theoretical models of complex networks from the hybrid model (HPM) to the harmonious unifying hybrid preferential model (HUHPM), and then toward the large unifying hybrid network model (LUHNM), which includes most current network models. The HUHPM and the LUHNM have revealed some nontrivial topological properties. The scale-free (SF) and the small-world (SW) properties strongly depend on the hybrid ratios controlling the attachment patterns in the model. Based on these models, one can understand the difference of degree-degree correlation for various types of complex networks (technological, social and biological networks). The LUHNM is closer and adapt to the real-world networks by using suitably matched three hybrid ratios in harmonious unification for most complex networks. To sum up, the LUHNM networks reveal and represent essential and comprehensive mechanisms for un-weighted and weighted complex networks. How to construct an exact network model to agree with real-world networks has been one of the most challenging subjects for network science. We have made some efforts and progress in this topic. By considering accelerating speed growth into the LUHNM as third stage of the hybrid model, the hybrid model is improved further and three stages (HUHPM, LUHNM and LUHV SG) in the hybrid model frame are formatted completely, as shown in Fig. 1. Through numerically simulations and certain analysis, this article provides a preliminary study of the topological properties of the LUHV SG, mainly including degree distribution, degree-degree correlation (assortativity, rc) and clustering coefficient (C). As accelerating exponent α increasing, we find that degree distribution transit from power-law toward double exponential, then toward single exponential distribution as shown in Fig. 2. It can be seen in Fig. 3 that for given hybrid ratios, the value of rc shows nearly independent with accelerating exponent. C has positive correlations with accelerating exponent. Our results have potential of application in high-tech network, 226 Annual Report of China Institute of Atomic Energy 2007

Fig. 1 Evolving trilogy of our models from HUHPM to LUHNM, and then toward LUHV SG

Fig. 2 Portraits of cumulate degree distributions in LUHV SG that initial parameters are f/d=0/1 and g/r=0/1 a—α=0; b—α=0.3; c—α=0.6; d—α=0.9

○—d/r=1/49; ●—d/r=1/4; ▲—d/r=1/1; ■—d/r=4/1; □—d/r=49/1 FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Applied Mathematics and Computer Technology 227

which will be published elsewhere. Some interesting subjects, such as dynamic behaviors and its control in the LUHV SG networks, are still open for further researches on their analytical solution.

Fig. 3 Portraits of cumulate degree distributions in LUHV SG that initial parameters are f/d=1/1 and g/r=1/1 a—α=0; b—α=0.3; c—α=0.6; d—α=0.9

○—d/r=1/49; ●—d/r =1/4; ▲—d/r=1/1; ■—d/r=4/1; □—d/r=49/1

* Supported by key projects of National Natural Science Foundation of China (70431002)

Small World Effect for HUHPM: Short APL

FANG Jin-qing, BI Qiao, LI Yong, LU Xin-biao, LIU Qiang

The SW effect discovered by Watts and Strogatz have both short APL and large ACC. Actually, this SW phenomenon is similar a famous poem of the in ancient China: ‘In the abroad there are the bosom friends, who bring afar distance region to neighbor’, that might demonstrate a wonderful and surprising prediction regarding the SW phenomenon in society and philosophy. It is very interesting that the previously proposed HUHPM network also merits these two SW characteristics, very short APL and very big ACC, except that their power exponent distributions are sensitive to the hybrid ratio. Below, we discuss these two characteristics using computed results and comparison with other models. Fig. 1 gives the relation of the shortest APL, L, and the hybrid ratio d/r for the three kinds of different preferential attachment orders (three HPAS-1-3). One can see that the L is not influenced by that of orders. For HUHPM- model, the change of L with the ratio d/r has three stages: The first stage in d/r<1/100, 228 Annual Report of China Institute of Atomic Energy 2007

belongs to randomness occupying the dominance, where L slowly drops, nearby 3.7 is almost invariable. The second stage starts in 1/100 < d/r < 1/1, the value of L rapidly drops from 3.7 to 2.3, the randomness gradually approaches the same level of proportion as that of determination, and d/r approaches the threshold value of d/r=1/1. Therefore, the shortest APL change is fierce. This is the very natural tendency. The third stage is in 1/1≤d/r<∞, the determination starts to occupy the leadership. The L value drops extremely slowly, probably from 2.3 it drops to 2 until it becomes invariable and arrives at the shortest APL, which is the shortest distance between the two most closely connected neighbor nodes. The SW effect displays specially and prominently. For the HUHPM networks, by numerical simulating, a relation of L and d/r is obtained by

ll12− Ll=+2 α (1) ⎛⎞dr/ ⎜⎟1+ ⎝⎠a

Where l1=3.797 54, l2=1.998 59, a=0.212 63, α=1.079 02 for the HUHPM-BA. Equation (1) shows that the shortest APL basically decreases with the power function of the hybrid ratio d/r and comes close to 2 after d/r≥10/1. This demonstrates that in the complete determination connection, the shortest APL is two nodes apart.

Fig. 1 Relationship of the shortest APL and the d/r for HUHPM-BA network under three different HPAS orders (a),

HUHPM-BBV model (δ>1) (b), and HUHPM-TDE model (w<1) (c) where N=6 000 and m=m0=3 a: ●—HPAS-1, ◁—HPAS-2, □—HPAS-3;

b: □—δ=0, ◆—δ=1, △—δ=2, ●—δ=4, ○—δ=5;

c: △—w=0, ◆—w=0.05, □—w=0.3, ◁—w=0.7, ○—w=0.9

Toward a Harmonious Unifying Hybrid Model for any Evolving Complex Networks

FANG Jin-qing, BI Qiao, LI Yong, LU Xin-biao, LIU Qiang

The basic concept and method for the HUHPM can be expressed in Fig. 1. This means that the HUHPM can rest on any type of network’s original growth way and RPA pattern by adding the DPA pattern according to arrangement of the degree distribution from big to small value (also may broadly develop other determination connection methods). This implementation combines the random connection with the determination connection by using the hybrid ratio to request growth scale FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Applied Mathematics and Computer Technology 229

size of the networks. Hence, the unified hybrid ratio can be defined as d/r, where d is a number of time intervals (step) for DPA, and r is a number for RPA. In the process of the network evolution, the hybrid ratio must maintain the same value by combining RPA and DPA. Actually, the kind of preferential attachments carried on at first is flexible. This means that one can use different order to make the two hybrids grow the network in turn, until the required scale size is achieved. The main mechanism and principle for implementation of hybrid growth network are as follows.

Fig. 1 Basic concept and method for HUHPM

1) The growth way First, use each growing rule of the model to carry on the growth. For example, the un-weighted BA model starts growth from less isolated nodes, the quantity is m0, then it increases in each time-interval to reach a new node with m (≤m0) edges and connects this new node to m different existing nodes. For the weighted BBV model, it allows to produce new edges among the old nodes, while for the TDE model, it grows a new node at each time step. The new node connects to the old nodes with m new edges, and then the network continues to grow this way. 2) Growth connection way Each step adopting the kind of connection mechanism must accord to the hybrid ratio d/r. Under the final d/r remaining invariance, there are three kinds of hybrid connection orders: HPAS-1: First carrying on RPA, then arranging rank of the degree of nodes from the biggest to the smallest, selecting m biggest degree nodes to carry on DPA. HPAS-2: First DPA then RPA. HPAS-3: RPA or DPA is carried on randomly. 3) DPA way After each attachment, rank of the degree of nodes is reordered again from the biggest to the smallest: k1 >k2 >···>km >···>kn, then m nodes are attached preferentially. This is a general way for DPA, which is quite natural. 4) RPA way Apply the above ideas and method to some current typical models, and follow the above steps to give the rules of the three present models BA, BBV and TDE, or as mentioned above, the so called HUHPM-BA, HUHPM-BBV and HUHPM-TDE network. The concrete constructions are 230 Annual Report of China Institute of Atomic Energy 2007

followed by their respective preferential attachment ways.

Synchronization Control of Periodic State in BTN With SW Topology

LIU Qiang, FANG Jin-qing, LI Yong

BTN systems are as follow: dx 1 = x dt 2 dx K 1 2 2 =−(cos)ab + x31 x + +3 + G dtxx11 dx 3 = ω dt

Fig. 1 shows the time evolution of variable x1 and x2 with time T in the BTN without any small world topology and the initial conditions are taken randomly from (x1(0), x2(0), x3(0))=(1.0, 0.5, 2π) and the parameters a=1.65, b=1.25, ω=2π and K=5, respectively.

Fig. 1 Evolution of variable x1 (a) and x2 (b) with T

We can not only realize synchronization control of halo-chaos as shown in last section, but also can reach the realize stabilized periodic state in the BTN with the small world topology only if the controller is designed as a special form of: N Gcax=Γ−−=∑ ij j 225( x 1), i 1,2," , N (1) j =1 where coupling strength c=0.1 and the initial conditions of every halo-chaotic oscillator are different: x1∈[0, 2], x2∈[0, 1], x3=2π, the BTN size N=100, K=6. The periodic oscillations and their control error curves are shown in Fig.2 and Fig.3 using the WS model and the SD model, respectively, where the network size N=100, K=6, and p=0.4. Obviously, the synchronization of the desired periodic one state in the BTN with the small world topology can be achieved only if the effective controller (1) is designed. It FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Applied Mathematics and Computer Technology 231

is seen from compared Fig. 1 with Fig. 2-3 that the halo-chaos is suppressed to be a stabilized period-1.

Original maximum amplitude of x1 oscillation is reduced from more than 3 to less 2.3 and the maximum amplitude of x2 is also reduced from more than 6 to 1.25. After controlling, the Lyapunov exponents become (－2.494 9, －2.506 1, 0), which mean that control goal of the halo-chaos is realized and periodic one is stabilized very quickly.

Fig. 2 Periodic oscillations of x1 and x2 with T in the BTN with small world topology a, b—WS model; c, d—SD model

c=0.2

Fig. 3 Periodic synchronization error curves for the BTN a—WS model; b—SD model

Dmax—maximum total synchronization error 232 Annual Report of China Institute of Atomic Energy 2007

Nuclear Safeguards Techniques

Detecting Technique for Characteristic Electromagnetic Signal of Uranium Centrifuge Enrichment Plant

LIU Guo-rong, LI Jing-huai, YE Feng, WANG Chen, LIANG Qing-lei

Gas centrifuge is the main process for enriched uranium production at present in the world. The high stage separation factor and energy efficiency, short equilibrium time, and small in-process material inventory make it an easy way for production of highly enriched uranium. So gas centrifuge is such a sensitive technology that a monitoring technique for confirmation and verification of gas centrifuge activity outside the cascade hall is needed Gas centrifuges and special designed transducers, working at unique frequency and pattern, are particular equipments in centrifuge enrichment plant. Low frequency electromagnetic wave with unique frequency will be leaked out during the running. The electromagnetic wave is very difficult to transmit, and the intensity decreases very quickly with distance, but it is not easy to be shielded. In order to detect the leaked electromagnetic signal of centrifuge enrichment activity, a special designed equipment for detecting low frequency electromagnetic wave with high sensitivity and resolution has been built. The sensitivity of the equipment for detecting low frequency magnetic field is better than 1 pT, and the frequency resolution is better than 3 Hz. An on-site experiment has been finished in a centrifuge enrichment plant by the instrument. The best frequency for detecting the leaked electromagnetic wave from the plant has been determined, and the means of measurement and identification has been established. The study demonstrates simul- taneously that the characteristic low frequency electromagnetic wave of centrifuge enrichment activity can’t feed back to outer electric power network, because of the filters installed in the transducers and transformers. The intrusion of this technique is low because centrifuge enrichment activity can be confirmed and monitored by detecting the characteristic electromagnetic signal outside. It could be a potential method for International Atomic Energy Agency (IAEA) to monitor the running state of centrifuge enrichment plants. This technique can be used to detect and locate the undeclared facilities where uranium centrifuge enrichment is conducting.

Experiment for Measurement of Uranium Enrichment With Small-Size CZT Detector

LIU Hong-bin, LU Xue-sheng, JIN Hui-min

CZTs (CdTe or CdZnTe) are a new type semiconductor compound detector materials, with the energy resolution lower than HPGe detectors but significantly better than NaI(Tl) detectors in the γ FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Safeguards Techniques 233

spectra measurement. With the properties of small-size, light weight, long time working at the room- temperature and easily to be made as compact instruments, these detectors has been widely used in the field verification of nuclear safeguards. This work presents an experimental study on the enrichment measurement of uranium product from enrichment plant with the CdTe detector. The ICS-4000, a compact isotope identifier made by LAURUS SYSTEMS Corporation, USA, was utilized in the experiment. The ICS-4000 instrument equips with a 10 mm×10 mm×1 mm CdTe detector and a 2 048 (4 000 max) channels analyzer, with the gain 1 keV/channel and resolution 10 keV (±1.5%, 662 keV). After the experiment in laboratory, the so-called “infinite-thickness technique” was established for the uranium enrichment measurement and applied in the field application of the uranium product enrichment measurement. Uranium products from enrichment plants are always stored in the standard, large-size and thick wall cylinders. In such case, the “Single-ROI Count Technique”, often used by the high-resolution detectors, rather than the “Double-ROI Count Technique”, always used by the low-resolution detectors, can be applied directly. This will simplify the uranium enrichment calculation method and minimize the error from the background subtractions. At the field application, the measurement was applied to the UF6 products stored in the standard “30B” type containers with the enrichment of 3.4%, 3.7% and 4.2%, the relative standard deviation was better than 2.4% with the measurement time about 1 200 s. This method may be used for the tracking-verification of the fresh nuclear material production to minimize the variance occurring with the different measurement system.

Development of Portable Handheld Neutron Counter

MENG Yan-tai, ZHU Li-qun, WANG Xiao-zhong, YIN Hong-he

A portable handheld neutron counter (PHNC) for measuring some ambiguous material about their attributions under non-laboratory conditions was designed. The system was configured to operate in the total neutron assay mode for confirming neutron source or not and in the coincidence neutron assay mode for determining spontaneous fission neutron source, especially for quantitative assay of Pu. 240 PHNC’s detective efficiency is 8.14%. The low limit of detection is 0.492 mg of Pueff (measurement time is 1 000 s, under laboratory conditions). The mass of the PHNC is less than 15 kg. The device can meet rapid emergency measurement for ambiguous material.

Scheme Design of Combined Fuel Assembly Measurement Device

LIU Hong-bin, JIN Hui-min, ZHAO Yong-gang, LU Xue-sheng

Fuel assembly measurement is the base of the nuclear material inspection and accountancy at a fuel fabrication plant. Fuel assembly measurement includes nuclear material enrichment measurement, weight verification and unique ID identification. The enrichment measurement always requires the scanning of the different position of the fuel assembly to confirm the consistency of the nuclear material. This work presents a scheme design of the combined fuel assembly measurement instrument with multi-function and multi-purpose properties. 234 Annual Report of China Institute of Atomic Energy 2007

The combined fuel assembly measurement instrument consists of three parts: nuclear material enrichment measurement, electric weight verification and unique ID identification. The instrument is designed as a vertical frame structure to fit with the shapes of the fuel assembly. The fuel assembly to be measured will be loaded in the middle of the frame, the weighing transducer and the ID identification camera are fixed on the top of the frame, and the enrichment measurement system can be moved up and down step by step by the motor mounted on the side track of the frame. At the same time, the base, on which the fuel assembly was laid, may revolve with the angle of 45° each time, so as to supply the fixed measurement condition of the eight areas on the same vertical section. 1) The small-size CZT detector will be used for the enrichment measurement. The detector with the properties of small-size, light weight, long time working at room-temperature, and easily to be made, can be combined together with the shielding collimator as a miniature instrument. The instrument will be fixed on the vertical track and can be moved up and down driven by the stepped motor, so as to scan the different position of the fuel assembly. The fuel assembly can be rotated for the measurement of the eight areas on the same vertical section shown in Fig. 1. 2) The load cell module will be utilized in the weight verification system. The amount of the nuclear material in the fuel assembly can be determined by comparing the weight of the fuel assembly measured by the load cell module with the standard simulating fuel assembly. 3) The unique ID marked on the top-end of the fuel assembly will be identified by using a video camera. With the application of this combined measurement instrument, the enrichment scanning measurement, weight verification and sampling ID verification of the fuel assembly can be performed at the same time and the on-site burden and effort can be significantly reduced. The system also may be used as an unattended measurement station with some improvement in the control and measurement performance.

Fig. 1 Detector and measurement area

Establishment and Development of CAEA-IAEA Joint Training Center on Nuclear Safeguards and Security

SHEN Ning

CAEA (China Atomic Energy Authorty)-IAEA Joint Training Center on Nuclear Safeguards and Security (here in after referred to as “Training Center”) was established in December 2006. Dr. El Baradei, Director General of IAEA and Mr. SUN Qin, Chairman of CAEA attended the unveiling FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Nuclear Safeguards Techniques 235

ceremony for the Training Center. The scope of Training Center involve conducting technical training on non-destructive assay nuclear material protection, physical control and accounting and providing expertise support to CAEA and the Agency. Especially in 2007, Training Center also provides training on nuclear security, radiation detection, identification and emergency response to support the security for Olympic game to be held in Beijing, august 2008. Over 15 groups from national or international organizations visited training center in 2007, including Deputy Director General of IAEA, director of department of safeguards, Mr. Olli Heinonen, and director of department of nuclear safety and nuclear security, Mr. Yuri Sokolov and Mr. Tomihiro Taniguchi.

1 Technical training Training Center successfully held a “scenario-based” international training course on radiation emergency response with Global Initiative to Combat Nuclear Terrorism in December 2007. Two regional training course on nuclear material protection, control and accounting with IAEA. Several national training courses coorperated with U.S. Department of Energy. Totally, Training Center provides training to around 300 participants from Australia, Brazil, China, France, Germany, India, Indonesia, Iraq, Japan, Bangladesh, Myanmar, Morocco, Netherland, Pakistan, Korea, Russian Federal, Spain, Sri Lanka, Sweden, UK, USA and Vietnam in 2007.

2 Technical seminar In order to increase the training capability, Training Center developed nine technical seminars with US Department of Energy. Topics on improvement of training conditions, development of new tech- nique and methodology, and design of new training courses involving non-destructive assay, radiation security and identification and mitigation of insider threat were discussed during these seminars.

Development of α-Waste Measurement Equipment for 200 L Drum

ZHU Li-qun, MENG Yan-tai, XU Xiao-ming, WANG Xiao-zhong, JIAO Xian-jun, BAI Lei, SHEN Ning, GAN Lin

With development of nuclear industry, more and more radioactive waste will be produced. All wastes have to be measured before disposing of them. According to Chinese Regulations of Radioactive Waste Management (GB 9133—1995), solid radioactive waste must be distinguished into a class of α-radioactive waste or not. That is very meaningful to reduce the cost of disposing the radioactive waste. We will use passive neutron assay method to measure 200 L waste drum, quantifying the radioactive waste so as to distinguish α-radioactive waste. At present, we have finished the equipment of physical design, blueprint, simulations of equipment have been taken by use of Monte-Carlo method, the electronics and measurement software are also under developing. This work will be finished at the end of year 2008. Now, research works are going in term of plan. 236 Annual Report of China Institute of Atomic Energy 2007

Radiation Protection and Environmental Protection

Simulation of Concentration Distribution of 3H in CIAE Groundwater

CHEN Chao, XIE Jian-lun

This work studied the concentration distribution of radionuclid, 3H in the groundwater of 5 km wide, 10 kilometers downriver around CIAE. The program FEMWATER/FEMWASTE developed by National Oak Ridge Laboratory is used to solve problems. And the parameters of the program are selected based on the local experimental material and responding references. The main equation in FEMWATER is Richards Equation and its modifications. The main solute migration mechanisms in FEMWASTE are convective flow, hydraulics diffusion, molecule diffusion, radioactive decay, adsorption, source-converge, and biological decomposition. During the computation, the mass balance of this zone is added and the penetration problem between several layers of aquifer can also be solved. This program is based on Galerkin finite element method with large flexibility in dealing with problems of time, space, initial conditions, sources and boundaries. On the basis of rectangle partition of this region, one-dimension column penetrate model and two- dimension level model are used to describe the migration of 3H in the unsaturated and aquifer groundwater. The boundaries and initial conditions are set according to the monitor materials about local hydrological geological condition, water level, concentration and so on. The concentrations of unsaturated and aquifer water are calculated in each time step and locational node, on the hypothesis of 3H entering into the groundwater in a certain concentration continuously. Then the results of unsaturated water are plotted into penetration curve and distribution curve along depth; the results of the concentration of 3H in aquifer are plotted into relative concentration isolines figures of this zone. Based on these figures, the migration behavior of 3H in unsaturated and aquifer is analyzed. The simulation results indicate that the penetration velocity of 3H is very small, about 0.001 m/d. The flow velocity is very uniform in nearly the same direction. A little solute moves up-and-down only on a small layer. The flow field basically points from north to south with a velocity of 1-10 m/d. The water head isolines decline steadily from northwest to southeast. The analysis of the relative-concentration distribution figures of 3H indicate that the migration of 3H in unsaturated water can be divided into three stages as time. The first one is penetration, in this stage the concentration declines with the increasing of depth. The 3H arrives at the bottom of unsaturated zone on the 840th day after the start of calculation. The second one is equilibrium stage, the concentration distribution of 3H inclines to equilibrium while the difference of concentration in different depth becomes smaller. The third one is accumulation, 3H accumulates in the bottom of unsaturated zone and the zero-flux boundary condition is not suitable any more. In aquifer, 3H migrates to downriver of the zone along the water flow, three kinds of source are simulated, which are point source, line source and plane source. Its relative concentration changes obviously in the horizontal direction while vertical direction changes slightly. The reason is that the horizontal diffusion coefficient is much lager than the vertical coefficient. And from the simulation we can FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiation Protection and Environmental Protection 237

see that in the whole zone the migration of 3H is restricted to the east of Dashi River, and an obvious long and narrow concentration belt appears in the migrating range. The difference among three types of the migration of 3H is that as a result of different shapes of source, the velocities and ranges are different even when the initial concentrations all the same.

Theoretical Calculation of Monoenergetic Electron Induced DNA Early Damage With Track Structure Method

YUE Feng, LIU Sen-lin

There are two main types of radiobiological effects, deterministic and stochastic effects, which concern radiation protection community. DNA molecular is the main carrier of heredity information. Its damage will induce the changing or missing of heredity information of organism directly. If the damage cann’t be repaired effectively and timely, it will lead to the mutation and apoptosis of cell. Over the past half-century, the important concerns to radiobiology scholars are the quantification of health hazards of ionizing radiation of different quality, and the reliability of human cancer risk from high-dose, dose rate extrapolation to low-dose, dose rate. With the rapid technological progress of molecular biology and the development of theoretical methods, the research and explanation of mechanism of ionizing radiation biology effects have become the focus of attention gradually over the past ten years. Track structure method is a theoretical foundation for understanding the basic mechanism of radiation damage. It follows the ‘track’ of various particles (including electron, proton of physical particles and radical of chemical particles), and provides a powerful tool to explore those parameters affecting the ultimate biological effects of ionizing radiation. The track structure method is used to model the early physical and chemical event from the incidence of monoenergetic electrons (10 eV-100 keV) to DNA solution to the production of final DNA-damage. The meaning of so-called ‘early’ refers to the stage before DNA repair, namely the physical and chemical stage, within about 10-5 s. The specific research topics are: 1) using MOCA15 code to calculate track distribution of certain energy electrons in aqueous media, and generating of the energy deposition of each event and the distribution of ionization and excitation of water molecular; 2) generating the distribution of free radicals in aqueous solution with the data of ionization and excitation data; 3) establishing the overall model and the fine structure model of DNA for simulation; 4) on the basis of this model, considering direct energy deposition and the free radical impacting and injuring DNA; 5) classifying the DNA damage, and generating the data of damage of all kinds to assess the biological effect induced by radiation. The research content is the modeling of the physical and chemical stage of low-energy electron-induced DNA damage with calculation program coded by C# computer language. The final production is the basic data of DNA damage, which contains the yield of double-strand break (DSB), single-strand break (SSB), and base damage (BD), and the analysis and comparison of the data. Through the analysis of the results, the following conclusions were drawn: 1) The majority of interactions in DNA don’t cause damage and are in the form of no break, most of the strand breaks are the SSBs which are easy to repair; 2) In a small number of DSBs, the complex DSBs accounted for a considerable number of shares (30%-50%); 3) From the source of injury, indirect damage accounts for a sizeable share, in particularly, makes a great contribution for constituting DSB; 4) According to the compare between results of theoretical calculations and experimental data, the basic assumption, DNA is the main target of radiation reaction, is validated. 238 Annual Report of China Institute of Atomic Energy 2007

Comparative Test of Glass Badge and OSL.TLD

XIAO Xue-fu, QIAO Hai-tao, MA Ji-zeng, WANG Kai, LI Hang, HE Li-hua

A comparative test of external dose measured by Glass Badge (GB), Optically Stimulated Luminescence dosimeter(OSL), and Thermo-Luminescent Dosimeter (TLD) was made by China Institute of Atomic Energy (CIAE) and Japan Chiyoda Technol Corporation (JCTC) from September to November, in 2007. The purpose of the comparative test is to test and improve the quality of individual monitoring of dose for both sides of CIAE and JCTC. There are 3 types of dosimeters for this comparative test, which are GB used in Japan Chiyoda Technol Corporation，OSL and TLD presently used in CIAE. Two periods of time are divided for the comparative test. In the first period of time, a set of dosimeters including 24 GBs, 24 OSLs and 24 TLDs were irradiated in China. Three doses of 0.3 mSv, 1 mSv and 10 mSv produced by X-ray with energy of 60 keV are chosen. Three doses of 0.5 mSv, 5 mSv and 10 mSv produced by a 60Co source are chosen. An ISO water phantom is used in the irradiation. In the second period of time, the same numbers of OSLs and TLDs were irradiated by JCTC. Three doses of 0.3 mSv, 1 mSv and 10 mSv produced by a 137Cs source are chosen. A PMMA Phantom（30 cm×30 cm×15 cm）is used in the second comparative test. After irradiation, OSLs and TLDs were measured by CIAE and GBs by JCTC, respectively. The measuring results are listed in Table 1 and Table 2.

Table 1 Results of comparison test (conference radiation in China)

Photon mean Dose in conference Calibration Hp(10) of GB Hp(10) of TLD Hp(10) of OSL

energy/keV radiation Hp(10)/mSv Phantom mSv error/% mSv error/% mSv error/%

60 0.3 0.29 －3.3 0.29 －3.3 0.23 －24

1 0.96 －4.5 0.88 －12 0.87 －13 ISO Water Phantom 10 9.20 －8.0 8.10 －19 8.71 －13. （30 cm×30 cm×15 cm） 1 250 0.5 0.53 5.0 0.53 6.5 0.51 2.5

(60Co) 5 5.38 7.6 5.18 3.6 4.94 －1.2

10 10.6 6.2 10.3 3.3 9.79 －2.1

Note：relative error=（dose measured－dose marked）/dose marked×100%; reference standard：ISO4037, X and gamma reference radiation for

calibrating dosimeters and dose-rate meters and for determining their response as a photon energy

Table 2 Results of comparison test (conference radiation in Japan)

γmean dose in conference calibration Hp(10) of TLD Hp(10) of OSL

energy/keV radiation Hp(10)/mSv Phantom mSv error/% mSv error/%

0.3 0.29 －3.3 0.30 0.0 661.7 PMMA Phantom 1 0.96 －4.0 1.03 2.5 (137Cs) （30 cm×30 cm×15 cm） 10 9.93 －0.75 10.5 4.8

From Table 1，we can see: FUNDAMENTAL AND APPLIED FUNDAMENTAL RESEARCH·Radiation Protection and Environmental Protection 239

1) The error of dose measured by GB is less than 8.0% for X-ray of lower energy, which is less than that measured by OSL and TLD. 2) The errors of dose measured are less than 2.5% for OSLs, less than 6.5% for TLDs, and less than 7.6% for GBs, for 60Co irradiation. It is not evident for difference of the errors among OSLs, TLDs and GBs. 3) All the individual monitoring accuracies of three types of dosimeter are met with the China National Standard—GBZ 128-2002 ‘Specifications of Individual Monitoring for Occupational External Exposure’. From Table 2, we can see that the errors of dose are less than 5%, which are not evident difference among OSLs, TLDs and GBs. In order to control the quality of comparison, following preparations are made by CIAE. 1) A set of OSLs and TLDs are irradiated by a 137Cs irradiation source. The OSLs and TLDs, whose disperses are less than 5%, are chosen as the dosimeters used for this comparison. 2) The TLDs are recalibrated by a 137Cs source in CIAE. The OSLs are recalibrated by a 60Co source in China Institute of Metrology Science (CIMS). 3) Each measuring value of dose given in Table 1 and Table 2 are averaged by those obtained ty 4 same kind dosimeters. 4) 4 controlling dosimeters for each kind of dosimeter are company with the whole process of transportation, and storage, except for irradiation, which are used for detracting backgrounds.

Characterization Survey During Decommissioning

WEN Fu-ping

With many research reactors and nucleus fuel recycle establishments entering into decommissioning stage in recent years, the characterization survey provides an important information for the subsequent decommissioning activities to perform safely and economically. Characterization survey provides a database of information on a facility about quantity and types of radionuclide, distribution of contaminants and physical or chemical nature of contamination. This information can help us to develop many estimates of decommissioning, such as waste volumes, appropriate technologies to use, worker safety requirements, etc. Our task in this project is to carry through the characterization about two sets of radioactive waste water evaporation pool (A and B) in a research institute. The radioactive waste water evaporation pools, forty years operating already, are the waste water disposal facility in this academy. Due to the complex source, the lose of historical information and one of them having the leak possibility in the past, it’s not easy to ascertain the contamination information. The other two difficulties consist in a waste burial well with unknown position and four hundred meters duct buried underground. A detailed survey plan setting down beforehand is necessary to accomplish this characterization survey successfully. We reinforce the situ-investigations to make up the lack of historical operating records and the structure of the radioactive waste water evaporation pool. A simple procedure and frame is re-draw by the mapper. The characterization is performed through two steps, one for the raw characterization and another 240 Annual Report of China Institute of Atomic Energy 2007

for the detail. Monitoring the environmental radioactive level, finding the reference background spot and estimating the position and level of the posssible historical waste water leakage belong to the first stage. The radioactive waste water evaporation pool are charactered with a twenty-five meters diameter and seven meters high wall. Five centimetres thick concrete, ten centimetres brick, two centimetres concrete, two centimetres pitch and one hundred centimetres sand are discovered in sequence from the surface to the underground in the floor of radioactive waste water evaporation pool. The wall consist of five centimetres thick concrete in the inner, ten centimetres brick in the middle and ten centimetres in the exterior. In the detail stage, we put emphases on the contamination location, distribution, radioisotopic makeup, radioactivity levels in different depth and place and areas classification. Certainly, gamma exposure rate measurement and gross beta and alpha surface contamination monitoring are the basic survey items for each section beforehand. Sampling is also the most important and efficacious way in this step. While sampling, three questions are consideried: Sampling method is adaptive and representative; Samples should be avoided cross-contamination; Sampling will not cause contamination to migrate. The radioactive waste water evaporation pools are unclosed, so dust-alleviation, sample damage protection and work keeping away from rainday are also insisted on in this project. The duct buried underground is one of the component of the two radioactive waste water evaporation pools and supposed to dismantle in this decommissioning. Some of the pipes, laid under the large building which isn’t part of this decommissioning, are impossible to carry out a full-scale characterization. On the one hand, we only measure and sample in the entrance, exit and joint, especially the cross-link valves. On the other, some calculations are considered to estimate the real radioactive level in each pipe. In the characterization survey of waste burial well, the bulldozer afford us a great convenience to locate the well. Delamination sampling is accepted for the soil under waste burial well. The measurements show there is no obvious contamination in the soil under the waste burial well.

IMPORTANT NUCLEAR INSTALLATION AND EQUIPMENT 243

Annual Report of HWRR in 2007

ZHANG Xing-wang

1 Operating time and released energy In 2007, the Heavy Water Research Reactor (HWRR) has been safely operated for 2 372 h and the energy released was 687.4 MW·d, with operating power level 6 500-7 300 kW. The operation statistics of HWRR in 2007 is shown in Table 1. CIAE decided to permanently cease HWRR operation since August 2007, taking into account that No.1 ionization chamber of power regulating system failed but no spare one can be used, while utilization reduced as well.

Table 1 Operation data of HWRR

Month Operating time/h Energy released/(MW·d)

Jan. 338 98.5

Feb. 244 71

Mar. 498 142

Apr. 284 80.4

May 410 119.5

June 502 142.2

July 116 33.8

2 Scientific research, production and maintenance 1) The second irradiation of special material was successfully accomplished, meeting all irradiation requirements. After discharge and storage in the spent fuel storage, two irradiation targets were moved to the hot cell for PIE at the end of 2007. 2) Irradiation of isotopes: 264 cans; irradiation of NTD silicon: 1 500 kg. 3) Nuclear physics experiments such as neutron scattering and neutron diffraction were conducted. 4) 12 fuel assemblies were refueled. 5) Automatic regulating rod No.1 was repaired, driving mechanism of shim rods No.5, No.6 and No.7 were examined. 6) Emergency generators No.47 and No.48 were repaired. 7) Heavy water pump A was overhauled. 8) Air sampling pump B was repaired. 9) Secondary coolant channels of main heat exchanger A and B were cleaned out. 10) Rad waste in the reactor hall was partially cleared and inflammable material in storage was collected and treated. 11) As part of modification of electricity grid at CIAE, transformers No.1 and No.3 of HWRR main building and transformer of secondary coolant system were changed. 12) 80 kg heavy water was supplemented to the reactor core. 13) Personnel training on radiation protection, operation procedures and emergency have been fulfilled according to HWRR annual training plan. 244 Annual Report of China Institute of Atomic Energy 2007

3 Progress in decommissioning 1) Proposal for permanent shutdown and transition of HWRR was submitted to Commission of Science, Technology and Industry for National Defense at the beginning of 2007. In September, it was evaluated by expert mission organized by New Era Engineering Consultant Co. Ltd., and supplemented material was submitted as required. Now, it is waiting for final approval of the commission. 2) Feasibility research report on spent fuel transport of HWRR and SPR was evaluated by expert mission and approved by the commission. 3) International cooperation includes as followings. IAEA TC project titled planning and technology for HWRR decommissioning was almost completed. Preliminary decommissioning plan of HWRR was reviewed by IAEA officer and experts and highly appreciated. At the same time, new TC project 2009—2011 titled decommissioning technology for HWRR was approved by the commission and submitted to the IAEA for approval in 2008. In addition, we also participated in other IAEA decommissioning programs, such as evaluation and demonstration of safety of decommissioning of nuclear facilities (DeSa), International decommissioning network (IDN), the research reactor decommissioning demonstration project (R2D2P). Implementing plan for cooperation agreement on nuclear science and technology between CNNC and SCK·CEN was signed in June. HWRR decommissioning is one of 6 projects. According to the plan, the cooperation agreement will be carried out since 2008 with personnel training and expert mission.

4 Disposal of radioactive wastes Gas wastes exhausted from stack: 41Ar, 1.936×1014 Bq; 3H, 1.5×1012 Bq; Total β, 2.963×106 Bq. Liquid wastes: 4 m3.

5 Fuel assemblies 69 fuel assemblies are loaded in the core, 329 spent fuel assemblies are stored in the spent fuel storage pool, and 16 fresh fuel assemblies in the fresh fuel storage.

6 Operators working on HWRR After HWRR cease operation, 33 staff was retained for transition phase and decommissioning while others move to new work. There are 8 operators, including 3 shift leaders and 5 operators.

7 Visitors More than 1 000 visitors including foreigners visited HWRR.

8 Nuclear power service Training for total 13 operators from Daya Bay Nuclear Power Plant has been completed on HWRR.

9 Abnormal events There are total 4 abnormal events occurred in 2007. 1) Loss of external power, HWRR scrammed. Two events of this type occurred. The reason for both events is voltage fluctuation for a short time, which triggered a relevant scram signal. 2) Heavy water leakage at main heat exchanger B. 3H concentration of secondary coolant sample reached 2.1×104 Bq/L, which is above operational IMPORTANT NUCLEAR INSTALLATION AND EQUIPMENT 245

limit. Further sample and analysis confirmed slight leakage of heavy water into secondary coolant. Consequently HWRR was shut down on April 5. Zone surface smear and measurement of 3H concentration of secondary coolant sample were used to identify the leakage source. H-3 concentration of samples around seals of two heat transfer tubes at line 8, column 8 and line 9, column 9 at inlet side of secondary coolant of main heat exchanger B was obviously higher than others. The fact showed that both seals were possibly the leakage source. After welding, H-3 concentration of secondary coolant reduced gradually, on April 13, it reached the background level. On May 18, 2007, 3H concentration of secondary coolant sample reached 3.9×104 Bq/L, which is above operational limit. Analysis showed slight leakage of heavy water from main heat exchanger B into secondary coolant. But a decision was made that power operation continued to find out the trend. After then, H-3 concentration of secondary coolant reduced gradually. On May 24, it reached 1×104 Bq/L, which is almost same as normal operational level, that is to say leakage ceased. Both events showed that the ageing of main heat exchangers caused possibility of malfunction increase. It also suggested that ageing management be strengthened, such as establishment of ageing database and surveillance of equipment status. All of 4 abnormal events were timely and correctly treated, thus no actual safety consequence on the reactor happened. They were also reported to the regulatory body within the requirement of abnormal event reporting program. After each event, different corrective and preventive measures have been established and implemented. Furthermore, through the process of judgment, analysis, treatment and discussion of the events, operational experience, lessons, capabilities and awareness are accumulated so as to ensure the operational safety.

MNSR Annual Operation Report

ZHU Guo-sheng

Guided by the nuclear safety roles，code and standards of China，MNSR performed safe operation in 2007. The annual operation report of MNSR in 2007 is as follows. 1) Licensees: 4 persons. 2) Operation times of 2007: 47 times. Full power operation among them: 0. 3) Total operation hours: 353.1 h. Equivalent hours for full power: 181.05 h. 4) Energy released: 4 888.35 kW·h. 5) Water guilty: Specific resistance is higher than 3×105 Ω·cm for reactor water; Specific resistance is higher than 2×105 Ω·cm for pool water. 6) Eleetricity consumption: 24 810 kW·h. 7) NAA Samples: 414 pcs. 8) Maintenance: Old fission chamber was changed with a new one. 9) Dosage: Within the dose limits. There are 16 persons inspected. Individual annual dose rage is 0.09-0.81 mSv; Total annual collective dosage is 5.79 man·mSv; Average annual individual dose is 0.36 mSv. Collective external expose: within regulatory limit. 246 Annual Report of China Institute of Atomic Energy 2007

HI-13 Tandem Accelerator in 2007

KAN Chao-xin, HU Yue-ming, BAO Yi-wen, FAN Hong-sheng

HI-13 tandem accelerator was running well in 2007, some good works were doing well in maintenance and development. In this year the machine has been operated 3 440 h, and provided beam time 2 970 h for more than 24 experiment users, the terminal voltage range is from 2 to 13 MV. In 2007, HI-13 tandem accelerator provided 19 kinds of ions and 2 970 h beam time. The distribution of beam time versus ion was shown in Fig. 1.

Fig. 1 HI-13 the distribution of beam time versus ion

The tank has been opened 6 times in 2007, besides replacing the stripper and normal maintenance the main work is dealing with some problems for the ladder Ron. Finished installing and modulating work for R70° branch beam line, all technical specifications are very good. R20° beam line developing work, finished designing and machining for the main devices, and are ready for the installation. The project for the accelerator radiation protection and safety technology development, now the main part of inviting tender and device ordering are finished. Finished designing for the control system of the main accelerator vacuum system, all the pumps and other devices were ready for installing. The accelerator and injector vacuum cooling system has been improved, saved the water resource largely. In 2008, the important work keep the accelerator running well, many things to do in maintenance and development, finishing the installation and modulation of the R20° branch beam line and the main work of the project for the accelerator radiation protection and safety technology development must be finished.

APPENDIX·International Scientific Technology Exchanges in 2007 249

International Scientific Technology Exchanges in 2007

China institute of Atomic Energy (CIAE) signed 2 international cooperation agreement and summary of minutes with Japan Chiyoda Technol Corporation. CIAE also organized successful and held some IAEA international workshops and training courses. CIAE sent 362 scientists, engineers and technical visitors joint academic exchanges. Among of them 149 persons attend international conferences, 213 persons went abroad on the studied tour, trained and worked though collaboration, including implementation contracts. CIAE received 705 foreign visitors that they came from 30 countries and regions. Foreign visitors gave more than 400 lectures. Among of them, 8 IAEA Technical Officers and IAEA Experts visited CIAE, they inspected and directed IAEA TC projects, also 1 IAEA Scientific Visitor and 1 IAEA Fellowship from Nigeria through IAEA program visited CIAE. A list of some visitors is given as follows: Jan. 10-28 Prof. Shuyao Fang from TRIUMF Canada’s National Laboratory for Particle and Nuclear Physics visited CIAE. Jan. 12 Prof. Pierre J. Paris, Deputy Director, from Paul Scherrer Institute, Switzerland visited CIAE. Jan. 14-21 Prof. Donald Bohringer from American Argonne National Laboratory visited CIAE and lectured on “Introduction on neutron scattering in Argonne National Laboratory”. Jan. 26 Mr. Taniguchi, Deputy Director General, International Atomic Energy Agency visit CIAE Nuclear Safeguards Laboratory. Jan. 27-31 Three engineers from Hungary Mirrotron Ltd. visited CIAE and discussed neutron guide installation and adjustment. Feb. 5-7 Prof. Guinyun Kim from Department of Physics, Kyungpook National University, Korea visited CIAE and discussed the cooperation. Feb. 6 Prof. Alan Shotter, Director, from TRIUMF Canada’s National Laboratory for Particle and Nuclear Physics visited CIAE, he lectured on “The progress of TRIUMF and nuclear astrophysics research”. Feb. 6-17 Prof. David Fink from Australia Nuclear Science and Technology Organization visited CIAE. He gave some lectures, the topics were “AMS research program in Australia”, “AMS measurements for isotopes of U, Pu” and “Application of AMS in environmental science”. Feb. 26-Mar. 3 Prof. Bruce Milton from TRIUMF Canada’s National Laboratory for Particle and Nuclear Physics visited CIAE, he lectured on “Design, construction and operational experiences of the TR cyclotrons”, he also evaluated for the 100 MeV H-Cyclotron design at CIAE. Mar. 2 Prof. Yasuo Nagashima, Koichi Akiyama, Tsutomu Takahashi, Satoshi Ishii, Yoshihiro Yamato from Tandem Accelerator Complex, University of Tsukuba, Japan visited CIAE, they lectured on “The current activities and the future plans of the the Tandem Accelerator Complex, University of Tsukuba”. Mar. 3-10 Four experts from Sandia National Laboratory, USA visited CIAE. Mar. 4-10 Prof. Hiroyuki Kikuchi from Nuclear Science Research Institute, Japan Atomic Energy Agency visited CIAE, he lectured on “Introduce about the structure of PIE facilities and techniques in 250 Annual Report of China Institute of Atomic Energy 2007

Tokai”. Mar. 7 Delegation of Japanese-Chinese Science and Technology Exchanges Society visited China Experimental Fast Reactor, Tandem Accelerator, Comprehensive treatment facility for radioactive liquids wastes at CIAE. Mar. 7-13 Through Sino-Japanese MEXT exchanges plan, Mr. Hiroaki Kumada from Japan Atomic Energy Agency visited CIAE and gave some lectures. Mar. 12 Delegation of Korea Atomic Energy Research Institute led by President Chang Kue Park visited China Experimental Fast Reactor site and Sodium Loop at CIAE, discussed the cooperation. Mar. 15 Delegation of Japan Atomic Energy Agency visited CIAE. Mar. 17 Prof. Harald Conrad from Germany Juelich Research Center visited CIAE and lectured on “Introduction on the TAS in Juelich”. Mar. 20 Prof. David Novog from University of McMaster, Canada visited CIAE and lectured on “Research activities of SCWR TH and safety in University of McMaster”. Mar. 24-30 Mr. V. IU. Sedakov from Russian OKB Mechanical Engineering visited CIAE and directed CEFR work. Mar. 27 Prof. D. C. Groeneveld from University of Ottawa, Canada visited CIAE and lectured on “Research on CHF, Post-CHF and heat transfer in SCWR”. Apr. 2-27 Prof. Chun-Keung Loong from American Argonne National Laboratory visited CIAE and directed neutron scattering work. Apr. 5 Mr. Mijonovak and Ms. Yu Mei from Austrian Hotwell Company visited CIAE. Apr. 6-20 Three experts from Russian OKB Mechanical Engineering visited CIAE and directed CEFR work. Apr. 12 Delegation of British Nuclear Fuels Plc (BNFL) visited CIAE. Apr. 14-July 15 Mr. Abdullahi Mohammad Alhassan from Centre for Energy Research and Training, Ahmade Bello University, Nigeria to CIAE, he was trainee three months at Miniature Neutron Source Reactor through IAEA fellowship, training in repair and mechanical maintenance of nuclear related equipment including fabrication of spare parts and small modules. Apr. 17 Delegation of Sweden Forsmark Gustav Dominicus visited CIAE. Apr. 22-25 Dr. Phil Ferguson, Dr. Allen Crabtree and Prof. Albert Yong from American Oak Ridge National Laboratory visited CIAE. Apr. 22-May 1 Prof. Nguyen Van Giai from Institute of Nuclear Physics, University Paris-XI, France, visited CIAE and lectured “Density dependent relativistic Hartree Fock approach”. Apr. 24 Dr. Steven Van Dyck (Deputy Institute Manager) and Prof. Da Ruan from Belgian Nuclear Research Centre visited China Experimental Fast Reactor, Comprehensive treatment facility for radioactive liquids wastes and Heavy Water Research Reactor at CIAE, they lectured on “Applied artificial intelligence in nuclear engineering systems” and discussed bilateral collaboration. Apr. 25-May 9 Two experts from Russian OKB Mechanical Engineering visited CIAE and directed CEFR work. Apr. 26 Delegation of Netherlands Nuclear Energy Agency visited China Experimental Fast Reactor. Apr. 27 Mr. Bouchter Jean-Claude and Mr. Durin Michel from Nuclear Energy Directorate of France APPENDIX·International Scientific Technology Exchanges in 2007 251

CEA, visited China Experimental Fast Reactor. Apr. 29 Dr. Robert Rosner (Laboratory Director) from American Argonne National Laboratory visited CIAE and lectured “The roles of national laboratories in the U.S. and the special case of Argonne National Laboratory”. May 7-31 Vachiliev Sergej Viktorvich and Filippov Andrej Nikolaevich from OKB Mechanical Engineering visited CIAE and directed CEFR work. May 8-15 IAEA Technical Officer Francoise Muelhauser and IAEA Expert Jamie Barras visited CIAE and directed TC item “Investigation of the detection of concealed explosives by nitrogen-14 nuclear quadruple resonance”. May 8 Forty-four technical personnel with the Delegation of Switzerland Plasma Physics Research Center led by Mr. Pierre J. Paris (Deputy Director) visited China Experimental Fast Reactor, Hot cell, Miniature Neutron Source Reactor, Quasi-molecule laser research at CIAE. May 10-11 Mr. Shen Ji-ge from Canada Ecometrix Company visited CIAE. May 10-15 Managers Mr. Rotzer Matthias and Mr. Vinkovits Sandor Peter from Austrian BITT Technology Company installed and adjusted radiation protection instrument. May 12-31 Three experts from Russian OKB Mechanical Engineering visited CIAE and directed CEFR work. May 14-31 Prof. Rex N. Taylor from Southampton University UK visited CIAE and lectured on “Measurement of Environmental Uranium and Plutonium Isotopes”. May 16 Delegation of Science and Material Division of CEA, France visited CIAE. May 17 Delegation of Japanese Chiyoda Technol Corporation led by President Toshikazu Hosoda visited CIAE. May 21-June 3 Expert Ivaneneko V. N. from Russian OKB Mechanical Engineering visited CIAE and directed CEFR. May 25-Jun. 31 Dr. Korolikov Anatolij Semenovich and Dr. Ohrimenko Aleksandr Ivanovich from Russian OKB Mechanical Engineering visited China Experimental Fast Reactor and discussed contract. May 26-Jun. 2 Mr. Luis Valencia, Mr. Cai Guo-yun, Mr. Harald Fritz and Mr. Qi Da-hai from Germany Forschungszentrum Karlsruhe visited CIAE. May 28 Prof. Philip Gardne and Ann Fong from TRIUMF Canada’s National Laboratory for Particle and Nuclear Physics visited CIAE. May 30-31 Prof. Sun Yang from University of Notre Dame, USA visited CIAE. May 31 《Regional Training Course on Combating Illicit Trafficking in Nuclear and other Radioactive Materials》participants twenty-nine visited CIAE Nuclear Safeguards. Jun. 4 Mr. Lionnel Mounier from GV Instruments Company, UK visited CIAE and lectured on “Application of TIMS in nuclear industry”. Jun. 7 Four experts from Russian RATEC Ltd visited CIAE. Jun. 8 Mr. Nabil Lutfi (Programme Management Officer) from Department of Technical Cooperation, International Atomic Energy Agency visited and inspected CIAE implemented TC items. Jun. 16-27 Dr. Jing Chen from Radiation Protection Bureau, Canada Health Ministry visited CIAE and lectured on “The estimation of radon-induced lung cancer risks and new polices of indoor radon in 252 Annual Report of China Institute of Atomic Energy 2007

Canada”. Jun. 16-30 Prof. Gerardo Giovanni Dutto from TRIUMF Canada’s National Laboratory for Particle and Nuclear Physics visited CIAE, he gave some lectures, the topics were “Consideration and advice on the progress of the construction for CYCIAE-100 and the latest research status on cyclotrons at TRIUMF”, “An updated assessment on the past achievements and future collaboration between TRIUMF and CIAE”. Jun. 17-July 16 Dr. Shtynda Iurij Eygenievich from Russian OKB Mechanical Engineering visited CIAE and directed CEFR work. Jun. 17-27 Prof. Claudio Spitaleri, Dr. Aurora Tumino, Dr. Rosario Gianluca Pizzone and Mr. Giuseppe Gabriele Rapisarda from LNS, National Institute for Nuclear Physics, Italy visited CIAE and lectured on “Theory and Applications of the Trojan Horse Method”. Jun. 17-30 Three experts from Russian OKB Mechanical Engineering visited CIAE and directed CEFR work. Jun. 17-30 Prof. Joho Werner Walter from Paul Scherrer Institute, Switzerland visited CIAE. He gave some lectures, the topics were “General introduction on the latest research status on cyclotrons at PSI” and “Consideration and advice on the progress of the construction for CYCIAE-100”. Jun. 18-19 Mr. Andy Hurst and Mr. Ken Pearson from JM Tracerco Company, UK visited CIAE and discussed cooperation. Jun. 18-July 1 Dr. Jochen Helmut Tschierch from GSF-National Center for Environment and Health, Institute of Radiation Protection, Germany visited and lectured on “Thoron and its progeny in traditional dwellings and their contribution to inhalation dose”. Jun. 19 Prof. Masahiko Isshiki and Mr. Jian-yu Chai from Japanese Radiation Application Development Association, Mr. Katsuhiko Nishiwaki, Mr. Masaki Ajioka and Mr. Takayuki Kutsuwada from Japanese Toyota Motor Corporation visited CIAE. Jun. 22 Technical Officer Mr. Rodolfo Cruz Suarez from International Atomic Energy Agency visited CIAE and lectured on “IAEA occupation radiation protection programme, current status and future activities”. Jun. 25-29 IAEA Technical Officer Ms. Borislava Batandjieva and IAEA Experts Mr. Bernd Sohnius, Mr. Kenneth G. Percival, Mr. Joe Carignan visited CIAE, they directed TC item Decommissioning plan for Heavy Water Research Reactor, review of the draft decommissioning plan for HWRR. Jun. 27-July 6 Four experts from Russian OKB Mechanical Engineering visited CIAE and directed CEFR work. July 2-5 Mr. Jow Hong-nian and Mr. Kwan Pang Lau from American Sandia National Laboratories visited CIAE. Jun. 2-31 Delegation of Germany Hoppecke Company visited CIAE. July 3-25 Prof. Iouri Bylinskii from TRIUMF Canada’s National Laboratory for Particle and Nuclear Physics visited CIAE. He gave some lectures, the topics were “Multipacting of RF cavity, close-loop adjusting on amplitude and frequency stability under the condition of cavity load” and “Consideration and advice on the CRM RF system”. July7-Aug. 18 Mr. Amponsah-Abu and Mr. A. G. Amponong from Ghana Atomic Energy Commission visited CIAE, they were trained at Miniature Neutron Source Reactor. APPENDIX·International Scientific Technology Exchanges in 2007 253

July 10 Mr. A. J. Gonzalez from Argentina Radiation Protection Society visited CIAE and lectured on “Radiation and health”. July 26 Delegation of France CEA led by Mr. Jacques Bouchard visited China Experimental Fast Reactor and discussed cooperation. July 27 Pakistan Delegation led by Additional Foreign Secretary Mr. Tariq Osman Haider visited CIAE. Aug. 2 Delegation of International Atomic Energy Agency led by Deputy Director General Mr. Olli J. Heinonen visited CIAE nuclear safeguards, environment sample analysis, chemical analysis center. Aug. 11-21 Mr. Vinkovits Sandor PETER from Austrian BITT Technology Company visited CIAE and maintained instruments. Aug. 13-30 Prof. Zheng Li from American Brookhaven National Laboratory visited CIAE. Aug. 14-22 Two experts Korolikov Antolij Semenovich and Efimov Vladimir Nikolaevich from Russian OKB Mechanical Engineering visited CIAE and discussed contracts. Aug. 20-31 Two experts V. D. Belousov and L. A. Belousova from Russian OKB Mechanical Engineering visited CIAE and directed CEFR work. Aug. 22 Mr. Klaus Schymke and Mr. Gunter Achilles from Germany NCS Nuclear Cargo+Service GmbH visited CIAE. Aug. 22-29 Delegation of American Department of Energy visited CIAE Nuclear Safeguards Laboratory. Aug. 25-Sep. 8 Prof. Sergey Bondareuko, Prof. Svetlana Chernobay and Evgenia Bochina from Russian Petersburg Nuclear Physics Institute visited CIAE. Aug. 31-Sep. 13 Prof. Jorge Fernandez Niello from Argentina National Institute of Atomic Energy visited CIAE. Sep. 2-15 Through IAEA Scientific Visit, Mr. Sunday Adesunloye Jonah from Centre for Energy Research and Training, Ahmadu Bello University, Nigeria visited CIAE. Sep. 3-5 Mr. Yang Ren from American Argonne National Laboratory visited CIAE and lectured on “High-energy X ray and neutron scattering study of antiferromagnetism materials”. Sep. 3-14 IAEA Regional Training Course on the Physical Protection of Research Reactors participants thirty-one to CIAE, they visited Nuclear Safeguards, Tandem Accelerator and China Experimental Fast Reactor. Sep. 4-15 Prof. Vesnovskiy Stanislav and Prof. Vesnovskaya Irina from All-Russian Scientific Research Institute of Experimental Physics visited CIAE and lectured “Preparation of high-pure isotope of actinide elements and its application”. Sep. 8-17 Four experts from Russian OKB Mechanical Engineering visited CIAE and discussed contracts. Sep. 10-20 Prof. weijian Lu from Australian ANSTO visited CIAE and directed work. Sep. 11-26 Prof. Zygmunt Marek Lipnick from TRIUMF Canada’s National Laboratory for Particle and Nuclear Physics visited CIAE, he lectured on “consideration on the RF improvements of the CRM cyclotron at CIAE”. Sep. 14-15 Prof. Hans A. Weidenmueller from Max-Planck Institute of Nuclear Physics, Germany visited CIAE and lectured on “Quantum chaos in many-body systems: the case of nuclear spectra”. 254 Annual Report of China Institute of Atomic Energy 2007

Sep. 15-29 Five experts from Russian OKB Mechanical Engineering visited CIAE and directed CEFR work. Sep. 16-29 Two experts from Russian OKB Mechanical Engineering visited CIAE and discussed contracts. Sep. 17-21 Dr. Fernand Vermeersch and Mr. Robby Nijs from Belgium SCK/CEN visited CIAE, they lectured on “Installation and training on VISIPLAN”. Sep. 20-24 Dr. Michael Steiner from Germany HMI, Prof. Chun-keung Loong and five Professors from USA, Dr. Uschi Steigenberger from UK ISIS, Prof. Yasuhiko Fujii from Japan JAEA visited CIAE, they attend “Review of the Progress of Building Neutron Scattering Instruments Meeting”. Sep. 22-30 Prof. A. J. Koning from Netherlands Nuclear Research and Consultancy Group visited CIAE. He gave some lectures, the topics on “TALYS nuclear reaction code” and “General performance of the JEFF-3.1 nuclear data library”. Sep. 23-29 Dr. Daniel Paul BROC from France CEA visited CIAE, he gave some lectures, the topics were “General presentation of the PWR and fast reactor cores activities”, “Presentation of the SYMPHONY program”, “Fluid structure interaction elements” and “Current research program on the fast reactor cores”. Sep. 25 Delegation of American QSA International Ltd. led by Mr. Ted Pang visited CIAE. Sep. 26 Delegation of Jordan Nuclear Energy led by Special Government Advisor Mr. Kamal Jabra Saba Alaraj visited CIAE. Sep. 27 Prof. W. Scheid from Institute for Theoretical Physics, Giessen University, Germany visited CIAE and lectured on “Application of di-nuclear model to the synthesis of super-heavy nuclei and nuclear structure”. Oct. 8-12 Through Sino-French cooperation agreement, Prof. Joel Serge Guidez, Prof. Laurent Martin and Prof. Bruno Sylvain Fontaine from Phoenix Research Center of Atomic Energy Commission in France, Prof. Christian Latge from Center of Cadarache, Atomic Energy Commission in France, Prof. Gilles Francois from France AREVE-NP visited CIAE and attend “2nd CIAE-CEA Seminar on Commissioning and Operation of Fast Reactors”. Oct. 8-22 Prof. Yu. Sakharovsky and Dr. A. Sazonov from Russian PXTY University visited CIAE and lectured on “Separation of hydrogen isotopes”. Oct. 12-13 Prof. A. Gasparin from American NC A&T State University, Prof. Liping Gan from American University of North Carolina visited CIAE, they lectured on “Recent progress on the PrimEx experiment” and “The lifetime of the charge-less pion”. Oct. 14-24 Prof. Giovanni Bisoffi from Legnaro National Laboratory, National Institute for Nuclear Physics, Italy visited CIAE. Oct. 14-24 Dr. Jean Delayen from American Thomas Jetterson Laboratory visited CIAE and lectured on “Design and construction of the SC cavities and cavity control system”. Oct. 15-25 Prof. T. V. Golashvili, Prof. V. P. Chechev and Prof. S.Badikov from Scientific Data Center and V. G. Khlopin Radium Institute, Russian Federation for Atomic Energy visited CIAE. Oct. 15 Delegation of Japan Chiyoda Technol Corporation and Mr. Youichi Fujiie (Former President of Japan Atomic Energy Commission) visited CIAE and signed the cooperation agreement between CIAE APPENDIX·International Scientific Technology Exchanges in 2007 255

and Japan Chiyoda Technol Corporation. Oct. 16 Fifty persons with the Delegation of American New Century Nuclear Technology visited CIAE China Experimental Fast Reactor and Sodium Loop, Dr. Waltar Alan Edward (Former President of American Nuclear Society) lectured on “Status of Nuclear Energy in the United States”. Oct. 16-Nov. 15 Expert Shimbarev Evgeny and expert Golosovsky Leonid from Russian SSC RF Research Institute of Atomic Reactors visited CIAE and lectured on “Californium-252 neutron sources making techniques and equipments”. Oct. 22-26 IAEA Technical Officer Mr. Amgad Shokr and IAEA Expert Mr. Simon James Bastin visited CIAE and directed Heavy Water Research Reactor decommission plan. Oct. 29 Jordan Education Minister Dr. Khaled Toukan visited CIAE. Oct. 29-Nov. 5 Mr. Paul Schmor and Mr. Philip Gardner from TRIUMF Canada’s National Laboratory for Particle and Nuclear Physics visited CIAE, they lectured on “TRIUMF’s accelerator progress and plan”. Oct. 29-31 Mr. Cheng Bo from American Electric Power Research Institute visited CIAE and gave some lectures. Oct. 31-Nov. 11 Mr. Jean-Michel Dolo and Mr. Tristan Garcia from Laboratory National Henri Becquerel (LNHB), CEA-Saclay France visited CIAE, they lectured on “Organization of metrology in France and application for ionizing radiations at LNHB” and “Metrology of dosimetry ES/alanine at LNHB: Research and application”. Nov. 1-6 IAEA 7th Technical Meeting of Scientific and Technical Committee of the Joint Study on an Innovative Nuclear Energy System based on a Closed Nuclear Fuel Cycle with Fast Reactors was held by CIAE in Beijing. Sixteen participants from France, Russia, Japan, Korea, China and IAEA, they exchanged 12 reports, the topics were “Overall assessment of INS based on CNFC-FR”, “Proliferation resistance & physical protection”, “A global architecture for INS based on thermal and fast reactors with inclusion of CNFC”, “Reactor & FC safety”, “Identification of areas for collaborative R&D”, etc. Nov. 9 Delegation of France Atomic Energy Commission led by High Commissioner Mr. Bernard Bigot visited CIAE China Experimental Fast Reactor site. Nov. 10 Delegation of Canada AECL visited CIAE and discussed cooperation. Nov. 11-18 Prof. Wolfgang Tron from Switzerland Paul Scherrer Institute visited CIAE and lectured on “RF amplifier regulations of the central region model cyclotron for CYCIAE-100”. Nov. 12 Expert Yanchur Victor (Russian Scientific Production Association Lutch Institute) and Expert Korolev Yury (Russian Scientific-Technical Association Powder Metallurgy Institute) visited CIAE. Nov. 12-19 Prof. Kimikazu Sasa from Tandem Accelerator Center, University of Tsukuba, Japan, visited CIAE and gave some lectures. Nov. 13 Dr. Van Goethem Georges from Europe Commission Director General Research Unite Euratom visited CIAE CEFR. Nov. 13-16 Prof. Yavshits Sergey, Prof. Khlebnikov Sergey and Prof. Oleg Grudzevich from Russian V. G. Khlopin Radium Institute visited CIAE. They gave some lectures, the topics were “Review of Khlopin Radium Institute physical department activity in the field of nuclear data” and “Calculations of temperature-dependent fission barriers”. 256 Annual Report of China Institute of Atomic Energy 2007

Nov. 15 Mr. Kazuo Mukai (Director General) and Mr. Shoji Kotake from Fast Breeder Reactor Research and Development Center, Japan Atomic Energy Agency visited China Experimental Fast Reactor site. Nov. 17-25 Prof. Toshio Hirao from Japan Atomic Energy Agency visited CIAE and lectured on “Single-event effects studies at JAEA” and “Analysis of single-event phenomena in semiconductor devices using heavy-ion micro-beam”. Nov. 19-29 Prof. Michael Peter Laverty from TRIUMF Canada’s National Laboratory for Particle and Nuclear Physics visited CIAE and lectured on “Digital parameter estimation and simulation of RF cavity for adaptive control”. Nov. 19 Mr. Dennis B. Kelley from American Pacific World Trade Inc visited CIAE. Nov. 21-29 Prof. Passarello Santi Maria from LNS, Italy National Institute for Nuclear Physics visited CIAE and lectured on “Consideration and advice on the screw jacks regarding the main magnet of the elevating system for CYCIAE-100”. Nov. 29 Prof. Yong-Hwan Jeong and Prof. Jeong Yong Park from Korea Atomic Energy Research Institute visited CIAE and lectured on “R&D of advanced Zr-cladding in Korea” Nov. 29-Dec. 6 Prof. Pierre G. Bricault from Canada TRIUMF-TRI University Meson Facility visited CIAE. He gave some lectures, the topics were “Introduction of ISAC at TRIUMF” and “Development of ion source and target at TRIUMF”. Dec. 3-12 Five experts from Nuclear Reactor Research Institute, Russia National Science Research Center visited CIAE and directed CEFR work. Dec. 5-12 Prof. Sandor Szatmari and Prof. Janos Bohus from University of Szeged, Hungary visited CIAE. Dec. 7 Delegation of Korea IAEA RCARO led by Mr. Choi Kun Mo visited CIAE and lectured on “Introduction on Regional Cooperative Agreement for Research (RCARO), Development and Training Related to Nuclear Science and Technology for Asia and the Pacific”. Dec. 7-22 Prof. Caruso Antonino Salvatore from LNS, National Institute for Nuclear Physics, Italy visited CIAE and lectured on “Amplifier and cavity system parameter identification and RF buncher design”. Dec. 11-12 Three engineers from Germany AREVA NP visited CIAE. Dec. 27 Mr. Nobuaki Teraoka, Mr. Kaka Wananabe and Ms. Shan Li from Japan RIKEN visited CIAE. Dec. 28 Delegation of Niger Mines Ministry led by Secretary-General Mr. Amadou Abdoul Razak visited CIAE. Dec. 28 Vice Chairman Mr. Saroni Binjudi from Malaysia Education Fund visited CIAE.

APPENDIX·CIAE Seminars in 2007 257

CIAE Seminars in 2007

No. Topics Speaker Date

1 The update of two important concepts of radiological XIA Yi-hua 2007.03.28 protection

2 21th “May 4” Youth Symposium 2007.04

1) Synthesis and structural properties of new 3: 29-type HAN Song-bai rare earth-iron intermetallic compounds 2) The basic experimental study of boron neutron KONG Fu-quan capture therapy 3) The simulation research of the divergent neutron guide in neutron scattering project at China Advanced LIANG Feng Research Reactor 4) The experimental investigation on the low energy MA Ying-jun beam transport system

5) Studies of the pre-equilibrium fission SUN Xiao-jun

6) Degree of freedom for the 178Hf isomeric state TU Ya

7) Research of two-proton halo nuclei 29S ZHANG Gao-long

8) Research on performance of microcalorimeter for the LI Wei measurement of the activity of low-energy beta emitters 9) The applying of plate heat exchanger in heavy water HAN Hai-fen system of research reactor 10) The piping stress results analysis and the optimization of setting the supports and hangers of the DA Shou-tong reactor cooling system in CARR 11) Study on the improvement of low-order harmonics XIA Zhao-dong expansion method 12) Design and commissioning at test bed for CEFR DONG Sheng-guo control system of replacing subassembly machine 13) Fast reactor fuel subassembly hot working LIU Yi-zhe hydromechanics computation research 14) Simulation of the flowrate transients characteristics PENG Yan of two-phase flow in anti-siphon pipeline 15) Commissioning of technology parameters for large WANG Jin-chun size sodium purification device 258 Annual Report of China Institute of Atomic Energy 2007

16) Design verification of technology room 508 in ZHOU Li-jun CEFR core island 17) R&D of program for determining neutron spectra of CHEN Xiao-liang CEFR 18) Intensity analysis and assessment for reinforced WANG Lu-bo concrete rooms of CEFR 19) The determination of the stability constant of Zr(Ⅳ ) and U(Ⅵ ) complexation by acetohydroxamic BIAN Xiao-yan acid(AHA) and the study of the separation of Zr in PUREX U-cycle with AHA 20) Computer simulation of the co-decontamination HUANG Xiao-hong process in Purex 21) Development of series of the uranium isotopic ZHU Hai-qiao reference materials 22) Study of highly enriched Uranium age-dating by LU Xue-sheng γ-spectrometry 23) The research of U target preparation method with YANG Chun-li pulse molecular plating 24) Preparation of monoclonal antibody against CA125 FENG Shu-yuan and it’s applications in immunoassay 25) Preparation and in vitro and in vivo evaluation of HU Chun-lin 99Tcm-MAG3-Folate 26) Preparation and imaging studies of 99Tcm- EDDA/HYNIC-Lys0-TOCA and the synthesis of its LUO Lian-jiao carbohydrated derivative

27) CICAM radioactivity foil & insert data process WU Rui-feng

28) Synthesis of 3'-deoxy-3'-[18F]fluorothymidine YUE Wen-qiang

29) Chemiluminescence immunoassay kit for prostate- ZHANG Xue-feng specific antigen 30) Determination of bacterial endotoxin by kinetic turbidimetic assay 31) Labeling resin microspheres for radioembolization ZHAO Ming-qiang therapy with 125I 32) Application of KrF laser induced fluorescence GUO Zhi-xing microscopy to test the laser damage of optics

33) Multimode high voltage modulator TONG Xun-hua

34) Development of an digital control card based on HOU Shi-gang DSP APPENDIX·CIAE Seminars in 2007 259

35) Development of large area CdZnTe detector for MENG Xin satellite detection of X- and γ-rays 36) The research of γ high radioactivity plume detect WU Yi-hua system 37) Theoretical calculation of monoenergetic electron YUE Feng induced DNA early damage with track structure method 38) Software design of intelligent multi-channel spectro- YE Xian-zhou meter 39) Student are asked to solve problem with GAO Li-rong understanding-cultivate student’s open thinking ability 40) On the cultivation of the ability to induce and RUAN Ying-ge deduce of the middle-school students 41) Talk about the survival rate how to improve the end LI Xu-dong last phase glycuresis nephropathy haemodialysis patient 42) A clinical analysis of treatment on CUI Ying-xin woodruff-epistaxis patients by nasal endoscopy 43) Summary and think about the treatment of diabetes LIU Bing over 300 cases 44) Higher-level specialists’ career management HUO YING-ying research in CIAE 45) How to use the flow-controlling to strengthen the WEI Feng management of science and technology 46) Analysis on the legal risk and precautions in the ZHU Li-na labor employment system 47) The labouratory’s construction of the waste water LI Na treatment 48) Application of integrating desulfurization and dust YAN Bing-zheng removal in boiler’s dust remover system of CIAE

49) Patent infringement judgement by the case of 13C LIU Jia

50) General situation of Chinese nuclear science HOU Cui-mei technology magazine embodied with EI and analysis

3 Technical books and periodicals standard CHEN Hao-yuan 2007.05

4 Light water reactor front and uranium resources highly LI Yu-lun 2007.06.11 effective use 5 Is must balanced the experiment which and the LIU Bai-xin 2007.06.26 fundamental research the alloy compares 6 Accurate monoenergetic X-ray photo source which and TANG Chuan-xiang 2007.12.26 application scatters based on Thomsen

260 Annual Report of China Institute of Atomic Energy 2007

Subject of Prize of Science, Technology and Industry for National Defense

Grade No. Subjects Contributories prize 1 Basic research on the physics ZHAO Zhi-xiang, DING Da-zhao, XIA Hai-hong, SHI 1 and technology of accelerator Yong-qian, FU Shi-nian, CUI Bao-qun, LI Ji-gen, driven clean nuclear power HAN Yin-lu, ZHU Sheng-yun, XU Yong-li, GUAN system Xia-ling, LUO Zhang-lin, XIA Pu, ZHUANG You-xiang, JIANG Wei-sheng 2 γ-ray experimental and XIA Hai-hong, HOU Long, ZHOU Jing, JIANG 2 theoretical study of D-D Chong, FU Yuan-yong, ZHAO Zhi-xiang, HUANG reactions Zheng-de, MA Yin-qun, JIANG Wei-sheng 3 Search for proton halo nuclei LIN Cheng-jian, LIU Zu-huan, ZHANG Huan-qiao, 2 and neutron halo nuclei YANG Feng, MA Zhong-yu, LIU Jian-cheng, CHENG Bao-qiu, ZHAO Yao-lin, LI Zhi-chang, RUAN Ming 4 The application study of YANG Qi-fa, ZHEN Jian-ping, LI Zhong-kui, LI Xi, 2 Mo-3Nb single crystal XU Yuan-chao, , WANG Zhen-dong 5 Demonstration experiment for DING Zheng-xi, CHEN Zhong-min, CHEN Yu-yu, 2 the Siphon breaking device of ZHANG Dong-hui, ZHANG Xue-feng, XU Mi, MU CEFR Zhong-fan, YANG Fu-chang, DU Kai-wen, WANG Wei, QI Xiao-guang 6 Development and application DONG Ming-li, TONG Bo-ting, ZHANG Qi-xi, LU 2 research of a spent fuel Wen-guang, LIU Guo-liang, LIU En-peng, LU assemiblies nondestractive Xiao-qing measurement system 7 Digital coincidence count YUAN Da-qing, WANG Jian-qing, CHEN Yun-dong, 2 technique for radioactivity LIU Qi-zhi, DA Yu-zhu, LI Xing, LI Qing-feng, measurement CHEN Xi-lin 8 Measurement and evaluation of LI Jing-wen, JIANG Li-yang, CHANG Hong-wei, 3 ratio of activation cross section CHEN Xiong-jun, ZHONG Qi-ping and fission cross section for 71Ga-23Pu and 180Hf-235U induced by neutron 9 Production and verification of ZHOU Pei-de, WANG Rao-qing, FANG Bang-cheng, 3 NVITAMIN-C library LIU Ping, YANG Yong 10 Research on the techniques of WANG Xiao-zhong, JIA Xiang-jun, MENG Yan-tai, 3 the active neutron coincidence LIU Da-ming, ZHU Li-qun assay for high density uranium-bearing material-a new active well coincidence counter

APPENDIX·CIAE Application of Patent in 2007 261

CIAE Application of Patent in 2007

Serial Apply item Assignee Appl. No. Style number 1 Siphon breaker YANG Fu-chang, DING Zhen-xin, 200710087008.6 invention devices ZHANG Dong-hui, SUN Gang 2 Preparation of 238Pu JIAN Li-min, WEN Zhong-ming, 200710087005.2 invention source of powder SUN Xia, YAN Shi-po, ZHANG metallurgy process Wen, GONG Ling-ling, SUN Yi-qiang 3 Preparation of 147Pm SUN Yu-hua, JIAN Li-min, FENG 200710087007.1 invention high concentration Jia-min, XU Rong-wang, LI source of powder Shi-ying, PING Jie-hong, DUAN metallurgy process Li-min 4 Method of the DNA NI Mei-nan, SUI Li, KONG 200710087006.7 invention sample preparation of Fu-quan, CAI Ming-hui mica were used as substrates 5 Method of the DNA NI Mei-nan, SUI Li, KONG 200710087010.3 invention sample preparation of Fu-quan, CAI Ming-hui APS-mica were used as substrates 6 Spent fuel assemblies DONG Ming-li, TONG Bo-ting, 200710087009.0 invention of physical data- ZHANG Qi-xin, LU Wen-guang processing methods 7 Nondestructive mea- DONG Ming-li, TONG Bo-ting, 200710087011.8 invention surements system of ZHANG Qi-xin, LU Wen-guang spent fuel assemblies 8 Gross gamma and DONG Ming-li, TONG Bo-ting, 200720140450.6 utility passive neutron detec- ZHANG Qi-xin, LU Wen-guang model tor system 9 Preparation method of YIN Bang-yao, NIU Kai 200710111255.5 invention

Li4SiO4 bauxite cera- mic spheres 10 Single point contact CHEN Dao-long, ZHANG Yan, LI 200710111257.4 invention type sodium leak Xin-ying detector of main envelope for sodium- cooled FBR 11 A alarm method of WANG Guo-bao, CHEN Yan-nan, 200710111396.7 invention radioactive monitor- YANG Lu 262 Annual Report of China Institute of Atomic Energy 2007

ing and mobile terminal 12 Induction type single CHEN Dao-long, KANG Rui-qing, 200710111397.1 invention point level gauge for LI Xin-ying liquid metal 13 Preparation process of YIN Bao-yao, GUO Cong-hui, 200710111398.6 invention γ phase U-Mo ahoy LIANG Xue-yuan powders 14 Sampler HONG Shun-zhang, ZHANG 200720151978.3 utility Xiu-feng, DU Hai-ou model 15 Neutron measure- WANG Zhong-qi 200710111256.x invention ment analysis devices 16 A device of staged WANG Zhong-qi 200720151979.8 utility γ-ray scanning survey model 17 The high temperature DONG Bi-bo, YU Hua-jin 200710130638.7 invention organic silicone oil for liquid sealer of fast reactor 18 Energy compensating ZHANG Wan-chang, HAO 200720151363.0 utility filter Xiao-yong, MENG Xin model 19 A method and device XIE Chun, JIA Yun-teng 200710151355.0 invention for directly dissolve sodium samples in distilled water 20 A facility of XIAO Hong-wen, CHEN Dong-feng, 200710151357.x invention hot-pressing germa- GOU Cheng, ZHANG Bai-sheng, nium crystal CHENG Zhi-xu, LI Ji-zhou, LIU Yun-tao, SUN Kai, WANG Hong-li, YU Zhou-xiang, WU Zhan-hua, ZHANG Li, LI Mei-juan, LI Jun-hong, HAN Song-bai 21 The hot-pressing XIAO Hong-wen, CHEN Dong- feng, 200710151358.4 invention deformation procedure GOU Cheng, ZHANG Bai-sheng, of the germanium CHENG Zhi-xu, LI Ji-zhou, LIU mosaic crystals Yun-tao, SUN Kai, WANG Hong-li, YU Zhou-xiang, WU Zhan-hua, ZHANG Li, LI Mei-juan, LI Jun-hong, HAN Song-bai 22 Water cooling system CAO Wen-feng, TANG Chao-hui, 200720177974.2 utility for main pump of HE Dan model sodium cooled fast reactor 23 Radioactive argon DONG Bi-bo, TANG Chao-hui, 200720177975.7 utility APPENDIX·CIAE Application of Patent in 2007 263

decay system of CAO Wen-feng, HE Dan model sodium cooled fast reactor 24 Lubricants cooling LI Ya-ping, WANG Yue-ying, MA 200720177976.1 utility system for sodium Yong-gang model circulating pump 25 A facility of hot- XIAO Hong-wen, CHEN Dong- 200720177977.6 utility pressing Germanium feng, GOU Cheng, ZHANG Bai- model crystal sheng, CHENG Zhi-xu, LI Ji-zhou, LIU Yun-tao, SUN Kai, WANG Hong-li, YU Zhou-xiang, WU Zhan-hua, ZHANG Li, LI Mei- juan，LI Jun-hong, HAN Song-bai 26 An absorption pool XIE Chun, JIA Yun-teng, GAO 200720177978.0 utility for analysis of trace Yao-peng model carbon. 27 Main vessel gas HE Dan, TANG Chao-hui, LIU 200720177979.5 utility heating system of Bao-quan, CAO Wen-feng model sodium cooled fast reactor 28 A sodium globe valve HE Dan, DONG Bi-bo, LIU 200720177980.8 utility Bao-quan, TANG Chao-hui, CAO model Wen-feng 29 A diffusion-based PEI Zhi-yong, HONG Shun-zhang, 200720177981.2 utility hydrogen meter MA Da-yuan, DOU Qin-min, model ZHANG Ke, MA Yong-gang, YU Hua-jin 30 A sodium purification ZHOU Yu-ying, PEI Zhi-yong, LI 200720177982.7 utility system for secondary Jing, QI Hong-yan model loop in sodium cooled fast reactor 31 Security detection CHEN Yu-hua, WANG Guo-bao, 200720181712.3 utility device for gamma CHEN Xin-nan, ZHANG Su-jing, model radiation WEI Quan-sheng 32 Security detection WANG Guo-bao, WEI Quan- 200720181713.8 utility device for artificial sheng, WANG Qiang, YAN Jing-ru model limb 33 Detection device CHEN Yu-hua, WANG Guo-bao, 200730320442.5 design of CHEN Xin-nan, ZHANG Su-jing, the shape WEI Quan-sheng 34 Argon distribution TANG Chao-hui, DONG Bi-bo, 200710195020.9 invention system of sodium MA Bing-zeng cooled fast reactor 264 Annual Report of China Institute of Atomic Energy 2007

35 A accident remaining XU Mi, LIU Lian-ping, YANG 200710195021.3 invention heat discharging Fu-chang, YE Yuan-wu, YU system for pool-type Hua-jin, LIU Jia-yi, , sodium cooled fast XU Yi-jun, YANG Zhi-min, reactor ZHANG Dong-hui 36 Boron carbide shield- ZHANG Ru-xian 200710195022.8 invention ing component 37 Sodium- sodium heat JIANG Ting-san, LIU Lian-ping, 200710195023.2 invention exchanger YE Yuan-wu, TANG Long, LIU Jia-yi 38 Sodium-air heat JIANG Ting-san, LIU Lian-ping, 200710195024.7 invention exchanger YE Yuan-wu, DONG Bi-bo, TANG Long 39 A sodium charging LI Jing, QI Hong-yan, PEI 200720310427.7 utility and discharging Zhi-yong, HONG Shun-zhang, LI model system for secondary Wen-hong loop in sodium cooled fast reactor 40 A sodium charging QI Hong-yan, ZHOU Yu-ying, PEI 200720310428.1 utility and discharging Zhi-yong, LI Wen-hong, MA model system for main Zi-yun vessel in sodium cooled fast reactor 41 Radioactive sodium ZHOU Yu-ying, DONG Bi-bo, 200720310429.6 utility in-line purified cold LIU Bao-quan, LI Jing model trap 42 A piping structure for LI Jing, QI Hong-yan, YANG 200720310430.9 utility sodium cooled fast Hong-yi, DONG Kang-le, SUN model reactor Xiao-fu, LI Wen-hong, YU Hua-jin 43 A sodium catch DU Hai-ou, SHEN Feng-yang, XU 200720310431.3 utility device for suppressing Yong-xing, -dong model sodium fire 44 Boron carbide ZHANG Ru-xian 200720310432.8 utility Shielding component model 45 An overpressure CHEN Gui-zhen, CAO Kang, 200720310433.2 utility protection device for WANG Bing, ZHOU Li-jun, PEI model pool-type sodium Zhi-yong, LIU Bao-quan, LI cooled fast reactor Wen-hong 46 Argon gas distribution TANG Chao-hui, DONG Bi-bo, 200720310434.7 utility system of sodium- MA Bing-zeng model cooled fast reactor 47 Tube for measuring HONG Shun-zhang 200720310334.4 utility cesium model APPENDIX·CIAE Application of Patent in 2007 265

48 Sodium-air heat JIANG Ting-san, LIU Lian-ping, 200720310335.9 utility exchanger YE Yuan-wu, DONG Bi-bo, model TANG Long 49 Sodium-sodium heat JIANG Ting-san, LIU Lian-ping, 200720310336.3 utility exchanger YE Yuan-wu, TANG Long, LIU model Jia-yi 50 Miniature high- XIE Chun, JIA Yun-teng, GAO 200720310337.8 utility temperature combus- Yao-peng, ZHANG Zhi-hou model tion furnace 51 γ-spectrometry colli- HONG Shun-zhang 200720310338.2 utility mator for sodium- model cooled fast reactor 52 An accident XU Mi，LIU Lian-ping, YANG 200720310339.7 utility remaining heat Fu-chang, YE Yuan-wu, YU model discharging system Hua-jin, LIU Jia-yi, TANG Long, for pool-type sodium XU Yi-jun, YANG Zhi-min, cooled fast reactor ZHANG Dong-hui 53 Radioactive sodium ZHOU Yu-ying, DONG Bi-bo, 200710198421.X invention in-line purified cold LIU Bao-quan, LI Jing trap 54 An overpressure CHEN Gui-zhen, CAO Kang, 200710198422.4 invention protection device for WANG Bing, ZHOU Li-jun, PEI pool-type sodium- Zhi-yong, LIU Bao-quan, LI cooled fast reactor Wen-hong 55 A sodium catch DU Hai-ou, SHEN Feng-yang, XU 200710198423.9 invention device for suppressing Yong-xing, WANG Rong-dong sodium fire 56 Method of DU Hai-ou 200710198424.3 invention disassembling pipes filled with liquid sodium-potassium alloy 57 A method of HONG Shun-zhang, DU Hai-ou, 200710306972.3 invention preparing NaK and WU Jie device 58 A method of NaK DU Hai-ou, HONG Shun-zhang 200710306973.8 invention charging and device 59 A filling and drainage QI Hong-yan, ZHOU Yu-ying, LI 200720309579.5 utility system of primary Jing, LI Wen-hong, MA Zi-yun model loop sodium in sodium-cooled fast reactor Note：National defence patent isn't included 266 Annual Report of China Institute of Atomic Energy 2007

List of Scientific Publication in Foreign Languages in 2007

1 Communications in Theoretical Physics, 2007 1) Theoretical analysis of neutron double-differential cross section of n+19F at 14.2 MeV, Vol.47, p.102. DUAN Jun-feng, YAN Yu-liang, SUN Xiao-jun, ZHANG Yue, ZHANG Jing-shang 2) Collective Hamiltonian for multi-O(4) model, p.309. GU Jian-zhong, et al. 3) Effects of scale-free topological properties on dynamical synchronization and control in coupled map lattices, Vol.47, p.361. (School of Automation Engineering, University of Electronic Science and 3.Technology of China), FANG Jin-qing, et al. 4) Synchronization and bifurcation of general complex dynamical networks, Vol.47, p.1 073. SUN Wei-Gang (Department of Mathematics, ), FANG Jin-qing, et al. 5) Exciton-dependent pre-formation probability of composite particles, Vol.47, p.1 108. ZHANG Jing-shang, WANG Ji-min, DUAN Jun-feng 6) Analysis of neutron double-differential cross sections for n+12C reaction below 30 MeV, Vol.48, No.3, p.534. SUN Xiao-jun, DUAN Jun-feng, WANG Ji-min, ZHANG Jing-shang 7) Shape coexistence in neutron-deficient at isotopes in relativistic mean-field model, Vol.48, p.705. LIANG Jun, MA Zhong-yu 8) Error thresholds in single-peak Gaussian distributed fitness landscapes, Vol.48, No.4, p.763. FENG Xiao-li (School of Physical Engineering, Zhengzhou University), GU Jian-zhong, ZHUO Yi-zhong, et al. 9) Synchronization and bifurcation analysis in coupled networks of discrete-time systems, Vol.48, No.5, p.871. SUN Wei-gang (Department of Mathematics, Shanghai University), FANG Jin-qing, et al.

2 Chinese Physics Letters, Vol.24, 2007 1) Influence of D-state in 4He on S factor for the 2H(d, γ)4He reaction, No.1, p.69. MA Yin-qun, TIAN Yuan, MA Zhong-yu 16 27 56 112 184 208 2) Mechanism of proton-induced reactions on targets O, Al, Fe, Cd, W and Pb at Ep=800 MeV, No.1, p.72. OU Li, ZHANG Ying-xun, LI Zhu-xia 3) Sensitivity of exponents of three-power laws to hybrid ratio in weighted HUHPM, No.1, p.279. FANG Jin-qing, BI Qiao, LI Yong, LU Xin-biao, LIU Qiang 4) Modified Woods-Saxon potential for heavy-ion fusion reaction, No.4, p.905. TIAN Jun-long, LI Zhu-xia, et al. 5) Measurement of gamma-rays from 11B and 12C, No.8, p.2 216. FU Yuan-yong, ZHOU Shu-hua, et al. 6) Neutron generation and kinetic energy of expanding laser plasmas, No.10, p.2 792. HUANG Yong-sheng, WANG Nai-yan, DUAN Xiao-jiao, LAN Xiao-fei, TAN Zhi-xin, TANG Xiu-zhang, et al. APPENDIX·List of Scientific Publication in Foreign Languages in 2007 267

7) The average lifetime of giant composite systems formed in strongly damped collisions, No.10, p.2 796. TIAN Jun-long, WU Xi-zhen, OU Li, LI Zhu-xia

3 Nuclear Science and Techniques, Vol.18, 2007 1) Modeling the leaching behavior of simulated HLW-glass using PHREEQC, No.3, p.150. ZHANG Hua, LUO Shang-geng 2) Preparation and biological evaluation of 99Tcm-labelled fatty acids, No.3, p.159. LIANG Ji-xin, HU Ji, CHEN Bao-jun, LUO Lian-zhe, LI Hong-yu, SHEN Lang-tao, LUO Zhi-fu 3) Analysis on natural circulation capacity of the CARR, No.3, p.186. TIAN Wen-xi (Department of Nuclear Science and Technology, Xi’an Jiaotong University), ZHANG Jian-wei, et al. 4) Evaluation of decay data of 213Bi, No.5, p.261. HUANG Xiao-long, WANG Bao-song

4 Journal of Physics G, Vol.34, 2007 1) Analysis of intermediate energy proton-induced spallation reactions by an improved quantum molecular dynamics plus statistical decay model, p.827. OU Li, ZHANG Ying-xu, TIAN Jun-long, LI Zhu-xia 2) Systematic study of fusion barriers, p.1 935. WANG Ning (Institute for Theoretical Physics at Justus-Liebig-University), LI Zhu-xia, et al.

3) Direct photon production in p+p and Au+Au collisions at sNN =200 GeV in the PACIAE model, p.S873. LI Xiao-mei, LI Shou-ping, HU Shou-yang, ZHOU Feng, SA Ben-hao

5 Nuclear Technology, Vol.159, 2007 1) The design, construction, and preliminary experiment of China’s ADS subcritical experimental assembly venus-1, p.106. SHI Yong-qian, XIA Pu, LUO Zhang-lin, ZHAO Zhi-xiang, DING Da-zhao, LI Yi-guo, ZHU Qin-fu, XIA Hai-hong, LI Ji-gen, ZHANG Wei, CAO Jian, QUAN Yan-hui, LUO Huang-da, WU Xiao-fei

6 Health Physics, Vol.93, 2007 1) The estimation of the number of underground coal miners and the annual dose to coal miners in China, p.127. LIU Fu-dong, LIU Sen-lin, CHEN Ling, MA Ji-zeng, et al.

7 Nuclear Data Sheets, Vol.108, 2007 1) Nuclear data sheets for A=196, p.1 093. HUANG Xiao-long

8 Journals of Alloys and Compounds, 2007 1) Morphology evolution of Ir-Nb-X(X=Hf, Ta, or Ti) ternary alloys, Vol.428, p.220. HUANG C, et al.

2) Formation, structure and magnetic properties of Nd3 － xZrxFe27.8Mo1.2 (0.1≤x≤0.5) compounds, Vol.431, p.68. 268 Annual Report of China Institute of Atomic Energy 2007

HAN S B, CHEN D F, LI J H, et al.

9 Nuclear Physics A, Vol.787, 2007 1) Effects of breakup of weakly bound projectile and neutron transfer on fusion reactions around coulomb barrier, p.281c. LIN C J, ZHANG H Q, YANG F, RUAN M, LIU Z H, WU Y W, WU X K, ZHOU P, ZHANG C L, ZHANG G L, AN G P, JIA H M, XU X X

10 Nuclear Instruments and Methods in Physics Research B, 2007 1) The development of a gas-filled time-of-flight detector, Vol.259, p.213. GUAN Yong-jing, HE Ming, WU Shao-yong, DONG Ke-jun, LIN Min, YUAN Jian, JIANG Shan 2) Measurement of 182Hf with HI-13 AMS system, Vol.259, p.246. QIU Jiu-zi, JIANG Shan, HE Ming, YIN Xin-yi, DONG Ke-jun, BAO Yi-wen, WU Shao-yong, YUAN Jian, YANG Bing-fan 3) Measurement of trace 129I concentrations in CsI powder and organic liquid scintillator with accelerator mass spectrometry, Vol.259, p.271. DONG K J, HE M, JIANG S, QIU J Z, GUAN Y J, LI S H, WU S Y, LIN M, YOU Q B, BAO Y W, HU Y M, ZHOU D, YIN X Y, YUAN J 4) A method for optimizing experimental conditions and simulating spectra in the measurement of heavy nuclides in AMS, Vol.259, 277. WANG Hui-juan, GUAN Yong-jing, JIANG Shan, HE Ming, DU Shu-bin, YUAN Jian, et al. 5) AMS measurement of 26Al cross section for the reaction 14N(16O, α)26Alg, Vol.259, p.629. HE Ming, JIANG Shan, YANG Yao-yun, DONG Ke-jun, WU Shao-yong, et al. 6) 99Tc measurements with accelerator mass spectrometry at CIAE, Vol.259, p.708. HE Ming, JIANG Shan, PENG Bo, DONG Ke-jun, GUAN Yong-jing, LI Shi-hong, WU Shao-yong, QIU Jiu-zi, YIN Xin-yi, DING Yan-qiu 7) Magnet design and construction preparation for CYCIAE-100 at CIAE, Vol.261, p.25. ZHANG Tian-jue, CHU Cheng-jie, ZHONG Jun-qing, YANG Jian-jun, XING Jian-sheng, LU Yun-long, WEI Su-min, CHEN Rong-fan, LI Zhen-guo, FAN Ming-wu 8) Spiral inflector and central region study for three cyclotrons at CIAE, Vol.261, p.60. ZHANG Tian-jue, YAO Hong-juan, GUAN Feng-ping, CHU Cheng-jie, LU Yin-long, JIA Xian-lu, ZHONG Jun-qing, YANG Jian-jun, XING Jian-sheng, LIN Yu-zheng 9) Beam line design for a 100 MeV high intensity proton cyclotron at CIAE, Vol.261, p.65. WEI Su-min, LU Yin-long, ZHANG Tian-jue, ZHOU Zheng-he, LI Zhen-guo, CHU Cheng-jie, WU Long-cheng, JIA Xian-lu, GUAN Feng-ping, PAN Gao-feng, YIN Zhi-guo, HOU Shi-gang, GE Tao, AN Shi-zhong 10) The alternative of RF system design for the 100 MeV cyclotron at CIAE, Vol.261, p.70. WANG Xiu-long, ZHAO Zhen-lu, JI Bin, ZHANG Tian-jue, YIN Zhi-guo, HOU Shi-gang 11) CYCIAE-100, a 100 MeV H－ cyclotron for RIB production, Vol.261, p.1 027. ZHANG Tian-jue, LI Zhen-guo, CHU Cheng-jie, for the Project Team 12) Calculation and analysis of proton-induced reactions on 58Ni at incident energies from threshold to 200 MeV, Vol.264, p.207. SHI Yu-yang, HAN Yin-lu 13) Calculation and evaluation of cross-sections for p+54, 56, 57, 58, natFe reactions up to 250 MeV, Vol.265, APPENDIX·List of Scientific Publication in Foreign Languages in 2007 269

p.461. HAN Yin-lu, ZHANG Yue, GUO Hai-rui

11 Physical Review C, 2007 1) In-medium NN cross sections determined from the nuclear stopping and collective flow in heavy-ion collisions at intermediate energies, Vol.75, 034615. ZHANG Ying-xu, LI Zhu-xia, et al. 2) Pygmy and giant dipole resonances in Ni isotopes, Vol.75, 054320. LIANG Jun, CAO Li-gang, MA Zhong-yu 3) Specific heat in hadronic matter and in quark-gluon matter, Vol.75, 054912. SA Ben-hao, LI Xiao-mei, HU Shou-yang, LI Shou-ping, FENG Jing, et al. 4) Isospin dependence of incompressibility in relativistic and nonrelativistic mean field calculations, Vol.76, 034327. Hiroyuki Sagawa (Center for Mathematical Sciences, The University of Aizu, Aizu-Wakamatsu), GU Jian-zhong, ZHANG Xi-zhen 5) Evolution of the proton SD states in neutron-rich Ca isotopes, Vol.76, 044319. M. Grasso (Institut de Physique Nucleaire, Universite Paris-Sud), MA Z Y, et al. 6) Low-lying E1 strength in light drip-line nuclei, Vol.76, 044321. LIN C J, ZHANG X Z, ZHANG R, LIU Z H, ZHANG H Q

12 Applied Radiation and Isotopes, Vol.65, 2007 1) Evaluation of 225Ac decay data, p.712. HUANG Xiao-long, WANG Bao-song

13 International Journal of Modern Physics A, Vol.22, 2007 1) Transverse ward-takahashi relation for the fermion-boson vertex vertex function in four-dimensional abelian gauge theory, No.11, p.2 119. HE Han-xin

14 International Journal of Modern Physics B, Vol.21, 2007 1) From a harmonious unifying hybrid preferential model toward a large unifying hybrid network model, No.30, p.5 121. FANG Jin-qing, LI Yong, BI Qiao

15 Science in China Series G, Vol.50, 2007 1) A harmonious unifying hybrid preferential model and its universal properties for complex dynamical networks, No.3, p.379. FANG Jin-qing, BI Qiao, LI Yong, LU Xin-biao, LIU Qiang

16 Physics of Plasmas, Vol.14, 2007 1) Hot-electron recirculation in ultraintense laser pulse interactions, with thin foils, 103106. HUANG Yong-sheng, LAN Xiao-fei, DUAN Xiao-jiao, TAN Zhi-xin, WANG Nai-yan, SHI Yi-jin, TANG Xiu-zhang

270 Annual Report of China Institute of Atomic Energy 2007

17 Journal of Theoretical Biology, Vol.246, 2007 1) Error thresholds for quasispecies on single peak Gaussian-distributed fitness landscapes, p.28. FENG Xiao-li (School of Physics and Engineering, Zhengzhou University), GU Jian-zhong, ZHUO Yi-zhong, et al.

18 Materials Research Bulletin, Vol.42, 2007

1) Synthesis of solid solution Er2－xCexW3O12 and studies of their thermal expansion behavior, p.2 090. WU M M (College of Chemistry and Chemical Engineering, Graduate University of Chinese Academy of Sciences), CHEN D F, et al.

19 Rare Metals, Vol.26, 2007

1) Crystal structures and thermal expansion properties of Y2－xErxMo4O15(x=0.0-2.0) solid solutions, No.5, p.426. CHEN Dong-feng, et al.

20 Front Energy Power Eng. China, Vol.1, 2007 1) China ADS sub-critical experimental assembly-venus-1 and preliminary experiment, No.2, p.150. SHI Yong-qian, XIA Pu, LUO Zhang-lin, ZHAO Zhi-xiang, DING Da-zhao, LI Yi-guo, ZHU Qin-fu, XIA Hai-hong, LI Ji-gen, ZHANG Wei, CAO Jian, QUAN Yan-hui, LUO Huang-da, WU Xiao-fei

21 Nuclear Instruments and Methods in Physics Research A, 2007 1) Measuurement of ultra-low potassium contaminations with accelerator mass spectrometry, Vol.582, p.381. DONG K J, HE M, JIANG S, QIU J Z, GUAN Y J, WU S Y, YUAN J

22 Journal of Nuclear Materials, Vol.367-370, 2007 1) Microstructural analysis on JLF-1 steel tested by fatigue deformation, No.1, p.147-152. LI Huai-lin, et al. 2) The effect of SiC nanowires on the flexural properties of CVI-SiC/SiC composites, No.1, p.708-712. YANG Wen, YANG Qi-fa, XU Yuan-chao, YU Ji-nan, et al.

23 Nuclear Science and Engineering, Vol.157, 2007 180,182,183,184,186,nat 1) Calculation and Analysis of n+ W reactions in the En≤250 MeV energy range, No.1, p.78. HAN Yin-lu, SHI Yu-yang, ZHANG Zheng-jun

24 Fusion Engineering and Design, Vol.82, 2007 1) Fatigue life and cyclic softening behavior of JLF-1 steel, No.15-24, p.2 595-2 600. LI Huai-lin, et al.

25 Ceramics International, Vol.33, 2007 1) Effects of heat treatment on the microstructure and flexural properties of CVI-Tyranno-SA/SiC composite, No.2, p.141-146. YANG Wen, YANG Qi-fa, et al. APPENDIX·List of Scientific Publication in Foreign Languages in 2007 271

26 Journal of Inorganic Materials, Vol.22, 2007 1) Effects of interlayer and matrix on properties of the advanced CVI-SiC/SiC composites, No.6, p.1 147. YANG Wen, YANG Qi-fa, et al.

27 Advances in Complex Systems, Vol.10, 2007 1) Toward a harmonious unifying hybrid model for any evolving complex networks, No.2, p.117. FANG Jin-qing, BI Qiao, LI Yong, LU Xin-biao, LIU Qiang

28 Physica A, Vol.383, 2007 1) Entropy and HUHPM approach for complex networks, No.2, p.753-762. BI Qiao, FANG Jin-qing

29 Progress in Nature Science, Vol.17, 2007 1) Theoretical research progress in complexity of complex dynamical networks, No.7, p.761. FANG Jin-qing

30 Romanian Reports in Physics, Vol.59, 2007 1) Search for possible way of producing super-heavy elements—dynamic study on damped reactions of 244Pu + 244Pu, 238U+238U and 197Au+197Au, No.2, p.729. LI Zhu-xia, WU Xi-zhen, et al.

31 Nuclear Engineering and Technology, Vol.39, 2007 1) Fast reactor technology R&D activities in China, No.39, p.187. XU Mi

272 Annual Report of China Institute of Atomic Energy 2007

List of Scientific Publication in Chinese in 2007

1 Journal of Chinese Mass Spectrometry Society, Vol.28, 2007 1) Studies on the measurement of isotope of trace plutonium in uranium by multi-collector inductively coupled plasma mass spectrometry (MC-ICP-MS), Suppl., p.8. LI Li-li, ZHAO Yong-gang, ZHANG Ji-long, WANG Tong-xing, et al. 2) Status of AMS at the china institute of atomic energy, Suppl., p.21. JIANG Shan, HE Ming, HU Yue-ming, YUAN Jian 3) Electromagnetic separation of stable isotopes, Suppl., p.42. LIN Zhi-zhou, LI Gong-liang, WANG Li-qin, JIN Kai 4) Determined the concentration of fission production 93Zr by MC-ICP-MS, Suppl., p.53. WANG Tong-xing, ZHANG Ji-long, ZHAO Yong-gnag, YANG Jin-ling, ZHANG Sheng-dong 5) Determination of uranium content and isotopic composition in environmental samples with high iron matrix by isotope dilution thermal ionization mass spectrometry, Suppl., p.88. ZHANG Wei, et al. 6) Certification of cadmium in ABS by isotope dilution mass spectrometry, Suppl., p.92. LU Hai, et al.

2 Chinese Journal of Nature, Vol.29, 2007 1) Does 3He in the interior of the earth is of “primordial origin”?, No.2, p.102. JIANG Song-sheng

3 Chemical Research In Chinese Universities, Vol.28, 2007 1) Influence of lithium salts anion and sidegroup of 15-crown-5 series on the far IR shift of solid lithium complexes with crown ethers, No.2, p.224. WEN Yong-hong (College of Chemistry and Chemical Engineering, Lanzhou University), YANG En-Bo, et al.

4 Chinese Journal of Radiological Health, Vol.16, 2007 1) Investigation of the level of radionuclide on 222Rn/220Rn and of γ dose rate in underground coal mines in Hebei province, No.1, p.14. LIU Fu-dong, WANG Chun-hong, et al.

5 Journal of Guangxi University: Natural Science Edition, Vol.32, 2007 1) Study on the chaotic synchronization communication of different structure SCH quantum well lasers, No.1, p.46. HUANG Liang-yu (College of Physical Science and Technology, Guangxi University), FANG Jin-qing, et al.

6 Modern Electronic Technique, Vol.30, 2007 1) Design of Thermal resister thermometer based on ARM, No.8, p.59. YANG Wei-tao, NI Bang-fa, et al.

APPENDIX·List of Scientific Publication in Chinese in 2007 273

7 Journal of Graduate School of Chinese Academy of Sciences, Vol.24, 2007 1) The neutron skin thickness and the equation of state for asymmetric nuclear matter, No.2, p.167. LIU Min, LI Zhu-xia

8 Chinese Journal of Radiological Medicine and Protection, Vol.27, 2007 1) Genomic instability induced by 60Co γ ray radiation in normal human liver cells, No.2, p.135. GENG Xiao-hua (Institute of Biotechnology, Shanxi University), WANG Zhong-wei, et al.

9 Chinese Journal of Computational Physics, Vol.24, 2007 1) Control of beam halo-chaos with soliton in a uniform-focusing channel, No.3, p.325. ZHANG Rong (Department of Physics, College of Science, China University of Mining and Technology), FANG Jin-qing, et al.

10 Chinese Health Economics, Vol.26, 2007 1) Status quo and issues of direct impatient cost of lung carcinoma in China, No.6, p.59. WANG Mei (China National Heath Economics Institute, MOH), LUO Zhi-fu, et al.

11 World Sci-tech R&D, Vol.29, 2007 1) Monte Carlo Simulation on Neutron Scattering Facilities, No.2, p.1. GUO Li-ping, SUN Kai

12 Chinese Journal of Lasers, Vol.34, 2007 1) Development of axial-transfer invariability and its application in mode-locking cavity design, No.6, p.748. ZHANG Xiao-hua, ZHANG Ji, TANG Xiu-zhang, et al.

13 Physical Testing and Chemical Analysis Part B:Chemical Analgsis, Vol.43, 2007 1) Photometric determination of hydroxyl free radical by its reaction with methylene blue, No.6, p.495. WANG Jin-gang, GU Zhong-mao, et al.

14 Journal of Beijing Institute of Petro-Chemical Technology, Vol.15, 2007 1) The application of network control system in low-energy high ion-current device, No.2, p.9. LI Kang-ning, LI Xing, YU Shuo, GUO Yan, et al.

15 Science & Technology Review, Vol.25, 2007 1) New features of assortativity characteristic transition in large harmonious unifying networks model, No.11, p.23. LI Yong, FANG Jin-qing, LIU Qiang 2) Production cross sections of Ba isotopes from the reaction of 60 MeV/u 18O with 232Th, No.12, p.50. YUAN Shuang-gui (Institute of Modern Physics, Chinese Academy of Sciences), ZHANG Sheng-dong, et al.

16 High Power Laser and Particle Beams, Vol.19, 2007 1) Applications of high to gas lasers at power pulse technology short wavelength, No.6, p.1 011. ZHAO Yong-peng (National Key Laboratory of Tunable Laser Technology, Harbin Institute of 274 Annual Report of China Institute of Atomic Energy 2007

Technology), YANG Da-wei, et al.

17 Radiation Protection, Vol.27, 2007 1) Focusing on clay formation as host media of HLW geological disposal in China, No.2, p.92. ZHENG Hualing (Science ＆ Technology Commission, China National Nuclear Corporation), FAN Xian-hua, et al. 2) Investigation and analysis of the content of natural radionuclides at coal mines in China, No.3, p.171. LIU Fu-dong, LIU Sen-lin, CHEN Ling, WANG Chun-hong, LIAO Hai-tao, WU Yi-hua, et al. 3) Status of determining transuranic nuclides speciation in aqueous solution, No.4, p.241. WANG Bo, LIU De-jun, YAO Jun, LONG Hao-qi, ZENG Ji-shu, SU Xi-guang, CHEN Xi, FAN Xian-hua

18 Energy Engineering, 2007 1) Benefits of nuclear power generation and status of world nuclear power development, No.1, p.1. SHI Yong-qian 2) Resolution for nuclear energy strategy of China, No.5, p.1. SHI Yong-qian, CAO Jian

19 Journal of Triticeae Crops, Vol.27, 2007 1) SSR analysis of M1 variation of dry seeds implanted by 7Li ion beam in wheat, No.4, p.560. XIN Qing-guo (The National Key Facility for Crop Gene Resources and Genetic Improvement/Institute of Crop Science, Chinese Academy of Agricultural Sciences), ZHAO Kui, SUI Li, KONG Fu-quan, et al.

20 Spectroscopy and Spectral Analysis, Vol.27, 2007 1) Determination of 235U/238U isotope ratios in camphor tree bark samples by MC-ICP-MS after separation of uranium from matrix elements, No.7, p.1 428. WANG Xiao-ping (School of Radioactive Medicine and Public Hygiene, Suzhou University ), ZHANG Ji-long

21 Uranium Geology, Vol.23, 2007 1) Development of a spectrum measuring instrument with spectrum-stabilizing for radon exhalation rate, No.2, p.109. FU Jin (Beijing Research Institute of Uranium Geology), PAN Da-jin, et al.

22 Radiation Protection Bulletin, Vol.27, 2007 1) Comparative proteomics and its application in radiation injury investigation, No.3, p.23. WANG Fang (China Institute for Radiation Protection), WANG Zhong-wen, et al.

23 Science Technology and Engineering, 2007 1) Multinucleon transfer reaction and cold fragmentation reaction of heavy nuclides, No.19, p.5 037. YUAN Shuang-gui (Institute of Modem Physics, Chinese Academy of Sciences), ZHANG Sheng-dong, et al.

24 Chinese Journal of Rare Metals, Vol.31, 2007

1) Preparation and properties of (ZrO2)0.96(Y2O3)0.03(Al2O3)0.01 ceramic, No.2, p.487. ZHOU Xin-yan, ZHANG Zhen-tao, SHA Shun-ping, ZHAO Lu, XIANG Lan-xiang, et al.

2) Investigation of hydrogen storage properties of LaNi4Al0.75M0.25（M=Mn, Sn, In, Ti, Zr） alloy, No.4, p.407. JIANG Yu-wei (Institute for Energy Materials and Technology; General Research Institute for APPENDIX·List of Scientific Publication in Chinese in 2007 275

Non-Ferrous Metals), YANG Hong-guang, et al.

25 Nuclear Physics Review, Vol.24, 2007 1) Theoretical models of cell inactivation by ionizing particles, No.2, p.94. CAO Tian-guang, KONG Fu-quan, YANG Ming-jian, ZHUO Yi-zhong 2) Motion of hydrogen bond proton in cytosine and transition between its normal and imino states, No.2, p.98. ZHAO Zhen-min (School of Physics, Peking University), ZHUO Yi-zhong, et al. 3) Effect of concentration of DNA and dose rate in DNA damage induced by γ ray, No.2, p.103. KONG Fu-quan, WANG Xiao, NI Mei-nan, SUI Li, YANG Ming-jian, ZHAO Kui 4) Initiatory pathologic observation of proton-irradiated mice’s organs, No.2, p.108. HUANG Hai-xiao (Beijing Institute of Radiation Medicine), SUI Li, KONG Fu-quan, WANG Xiao, ZHAO Kui, et al. 5) Radiation effect of spent fuel of nuclear power on biological circle and ADS strate, No.2, p.151. SHI Yong-qian 6) Measurement of decay rate variation of 7Be in Pd and Au, No.3, p.200. LI Cheng-bo, LIU Zhi-yi, ZHOU Shu-hua, ZHOU Jing, MENG Qiu-ying 7) A grid-ionization chamber and a ΔE-E particle telescope detection set-up, No.3, p.204. WANG Tao-feng, ZHU Li-ping, MENG Qing-hua, WANG Li-ming, HAN Hong-yin, XIA Hai-hong, LI Guang-wu, QU Cong-hui, GU Xian-bao 8) Nuclear data for production of therapeutic radionuclides (Continued), No.3, p.247. WANG Shu-nuan, LI Chun-sheng

26 High Energy Physics and Nuclear Physics, Vol.31, 2007 1) Wobbling magnet design for beam line of CYCIAE-30 medical cyclotron, No.3, p.292. JIA Xian-lu, ZHANG Tian-jue, LU Yin-long, AI Chang-jun, CHU Cheng-jie, GUAN Feng-ping, XING Jian-sheng 2) Development of the broadband and dual-band cavity mirrors for SR-FEL at 355 nm and 248 nm, No.4, p.405. GAO Huai-lin (Institute of Electronics, Chinese Academy of Sciences), WANG Nai-yan, et al. 3) Measurements of neutron emission, spectra for neutron induced reactions on 9Be and 6, 7Li, No. 5, p.442. RUAN Xi-chao, ZHOU Zu-ying, CHEN Guo-chang, QI Bu-jia, LI Xia, HUANG Han-xiong, ZHONG Qi-ping, TANG Hong-qing, JIANG Jing, XIN Biao, BAO Jie, CHEN Lin, ZHANG Jing-shang 4) Studies on Energy spectra of outgoing particles in (p, Pb), (p, Bi), (p, Hg) reactions in energy range up to 250 MeV, No.5, p.464. ZHANG Zheng-jun (Department of Physics, Northwest University), HAN Yin-lu, SHEN Qing-biao, et al. 5) Giant monopole resonance and symmetry energy, No.5, p.470. LIANG Jun, MA Zhong-yu 6) Investigation of radioactivity of uranium target in target-source of ISOL, No.6, p.548. YAN Fang, CUI Bao-qun, SHU Neng-chuan, LIU Ting-jin, WU Hai-cheng, FAN Sheng 7) Level structure with high excitation states in 134Ba, No.7, p.621. CHE Xing-lai (Department of Physics, Tsinghua University), ZHU Li-hua, WU Xiao-guang, LI Guang-sheng, LIU Ying, HE Chuang-ye, et al. 8) A method of evaluating discrepant data, No.7, p.629. HUANG Xiao-long, WANG Bao-song 9) Double folding model calculation applied to the real part of interaction potential, No.7, p.634. 276 Annual Report of China Institute of Atomic Energy 2007

ZHANG Gao-long, ZHANG Huan-qiao, LIU Zu-hua, ZHANG Chun-lei, LIN Cheng-jian, YANG Feng, AN Guang-peng, JIA Hui-ming, -dong, XU Xin-xing, BAI Chun-lin, YU Ning 10) Research on measurement of 182Hf with HI-13 AMS system, No.8, p.719. QIU Jiu-zi, JIANG Shan, HE Ming, YIN Xin-yi, DONG Ke-jun, WU Shao-yong, et al. 11) A two-dimension beam dynamics simulation code base on PIC method, No.8, p.769. YANG Jian-jun, ZHANG Tian-jue, AN Shi-zhong, JIA Xian-lu, et al. 12) Design of a digital LLRF control system for the 100 MeV high intensity cyclotron, No.10, p.962. YIN Zhi-guo, HOU Shi-gang, XIA Le, ZHANG Tian-jue, ZHAO Zhen-lu, WANG Xiu-long, JI Bin, LI Zhen-guo 13) Preparation of 182Hf AMS standard sample and test on HI-13 tandem AMS, No.10, p.978. YIN Xin-yi, HE Ming, DONG Ke-jun, QIU Jiu-zi, WU Shao-yong, GUAN Yong-jing, JIANG Shan, et al.

27 Acta Physica Sinica, Vol.56, 2007

1) Structure and magnetic properties of NiFe2O4 nanoparticles prepared by low-temperature solid-state reaction, No.10, p.6 050. LIU Jin-hong (Key Laboratory for Magnetism and Magnetic Materials of the Ministry of Education, Lanzhou University), TIAN Geng-fang, et al.

28 Journal of Inorganic Materials, Vol.22, 2007 1) Effects of interlayer and matrix on properties of the advanced CVI-SiC/SiC composites, No.6, p.1 147. YANG Wen, YANG Qi-fa, et al.

29 Rare Metal Materials and Engineering, Vol.36, 2007 1) Effects of steel melting furnace on surface films formed on magnesium alloys under N2/SF6 atmosphere, No.A3, p.21. NIE Shu-hong, et al. 2) Comparison of mechanical properties between the miniature disk and mechanism testing method for Mo-3Nb single crystal alloy, No.A3, p.351. ZHANG Qing (Northwest Institute for Nonferrous Metal Research), HENG Jian-ping, et al.

30 Industrial Control Computer, Vol.20, 2007 1) Emittance measurement instrument based on LabVlEW, No.11, p.88. LI Ai-ling, CUI Bao-qun, YANG Bing-fan, MA Rui-gang, LI Li-qiang

31 Nuclear Power Engineering, Vol.28, 2007 1) Safety consideration in design of closed loop control system for miniature neutron source reactor, No.1, p.87. CHEN Yu (Joint Institute of Applied Nuclear Technology, Shenzhen University), WANG Li-yu, et al. 2) Study on steady natural circulation capacity of CARR, No.2, p.13. TIAN Wen-xi (Department of Nuclear Engineering and Technology, Xi’an Jiaotong University), ZHANG Jian-wei, et al. 3) Development of a beam transient code for ADS, No.2, p.124. YU Tao (School of Nuclear Science & Technology, Nanhua University), LI Ji-gen, SHI Yong-qian, LUO Zhang-lin, RONG Yong-hua 4) Simulation research and optimal design for digital power regulating system of china advanced research APPENDIX·List of Scientific Publication in Chinese in 2007 277

reactor, No.5, p.104. DONG Hua-ping (Nuclear Power Institute of China), ZENG Hai, et al. 5) Criticality experiment for 2# core of DF-VI fast neutron criticality facility, No.6, p.13. YANG Li-jun, LIU Zhen-hua, YAN Feng-wen, LUO Zhi-wen, CHU Chun, LIANG Shu-hong 6) Validation of fuel behavior analysis code METEOR 1.5, No.2, Suppl., p.12. HE Xiao-jun, CHEN Peng

32 Journal of Shanghai University: Natural Science, Vol.13, 2007 1) Analyzing the induced radiation of high energy electron accelerator with the Monte Carlo method- Microcosmic analysis, No.1, p.68. HE Xin-fu (Shanghai Applied Radiation Institute, Shanghai University), YAN Fang, FAN Sheng, et al.

33 Journal of Guangxi Normal University: Natural Science Edition, Vol.25, 2007 1) Analytical solution of smoluchowski equation in harmonic oscillator form, No.1, p.13. SUN Xiao-jun, et al. 2) Birth of new science of networks and its development prospects, No.3, p.2. FANG Jin-qing

34 Chinese Journal of Nuclear Science and Engineering, Vol.27, 2007 1) R ＆ D status of China low activation martensitic steel，No.1, p.41. HUANG Qun-ying (Institute of Plasma Physics, Chinese Academy of Sciences), YU Jin-nan, ZHU Sheng-yun, ANG Pin-yuan, et al. 2) The microstructure and mechanical properties of China low activation martensitic steel, No.1, p.59. ZHAO Fei (School of Materials Science and Engineering, University of Science and Technology Beijing), XU Yong-li, et al. 3) Probing the problems of thorium utilization as a nuclear energy resource, No.2, p.97. GU Zhong-mao 4) Subcritical reactor dynamic characteristics research by accelerator beam trip in an accelerator-driven system, No.3, p.230. YU Tao (School of Nuclear Science ＆ Technology, Nanhua University), LI Ji-gen, SHI Yong-qian, LUO Zhang-lin, RONG Yong-hua, et al. 5) Fission-fusion neutron source, No.4, p.289. YU Jin-nan 6) Experiment study on neutron flux density space-time characteristic in ADS “Venus 1#”, No.4, p.310. CAO Jian, SHI Yong-qian, XIA Pu, ZHANG Wei, LUO Huang-da, ZHU Qing-fu, LI Yi-guo, QUAN Yan-hui 7) Flow-induced vibration analysis for the lower internals of PWR, No.4, p.333. LU Dao-gang (Department of Nuclear Engineering; Electric Power University; Key Laboratory of Condition Monitoring and Control for Power Plant Equipment of Ministry of Education ), LUAN Lin, ZHANG Zhong-yue 8) Design and realization of network control system based on virtual instrument in the field of accelera- tors, No.4, p.359. LI Kang-ning, LI Xing, YOU Qu-bo, YU Shuo, GUO Yan, BAO Yi-wen

278 Annual Report of China Institute of Atomic Energy 2007

35 Progress In Physics, Vol.27, 2007 1) New interdisciplinary science: Network science (I), No.3, p.239. FANG Jin-qing, WANG Xiao-fan, ZHENG Zi-gang, LI Xiang, DI Zeng-ru, BI Qiao 2) New interdisciplinary science: Network science (II), No.4, p.361. FANG Jin-qing, BI Qiao, et al.

36 Journal of Atomic and Molecular Physics, Vol.24, 2007 1) X-ray diffraction line-profile analysis of nanocatalyst Pt/C, No.6, p.1 147. FAN Zhi-jian (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics), LI Guang-wu, et al.

37 Nuclear Electronics & Detection Technology, Vol.27, 2007 1) Neutron flux density measurement system in commercial mini-neutron-source-reactor, No.2, p.304. YIN Lin-feng (Hefei Zhengyang Photo-electricity Ltd.), WANG Li-yu, et al. 2) Application of QH2001 in automatic irradiation system for reactor neutron activation analysis, No.2, p.412. SHEN Li, NI Bang-fa, et al. 3) Dependence of incident area for HPGe detecting efficiency, No.4, p.624. LI Tao-sheng, et al. 4) Reactor power control hardware-in-the-loop simulation in nuclear power station base on the internet remote control, No.4, p.643. YU Tao (School of Nuclear Science & Technology, Nanhua University), ZHU Ji-yin, et al. 5) An improved method for 129I-AMS measurement, No.4, p.740. ZHOU Ben-hu, JIANG Shan, WU Shao-yong, HE Ming, YUAN Jian, et al. 6) Segmented gamma scanning method for measuring holdup in the spherical container, No.5, p.895. DENG Jing-shan (The Fifth Research and Design Institute, CNNC), LI Ze, GAN Lin, LU Wen-guang, DONG Ming-li 7) A comparison on determining activities of 238U and 232Th based on transfer samples and some associa- tions of ideas for some investigation passed of environment radiation, No.5, p.914. SU Qiong (Institute of Nuclear Technology, Department of Engineering Physics, Tsinghua University), DIAO Li-jun, LI Gui-qun, et al.

38 Isotopes, Vol.20, 2007 1) Preparation and biological study of 99Tcm(N)(PNP6)(Cys-RGD) for Integrin αvβ3-positive tumor imaging, No.1, p.5. CHEN Bao-jun, HU Ji, LIANG Ji-xin, LI Hong-yu, LUO Lian-zhe, SHEN Lang-tao, LUO Zhi-fu 2) Biological properties evaluation of a novel glycosylated somatostatin labeled with 99Tcm, No.1, p.11. HE Chuan, DU Jin, et al. 3) Development of a CA19-9 immunoradiometric assay, No.1, p.16. YAN Qiang-fen, CHEN Yong-li, WANG Yan-zhen 4) The establishment of a competition inhibition ELISA for sulfamethoxazole, No.1, p.20. FENG Ting-ting, LI Zi-ying, LIU Yi-bing, XU Wen-ge, GUAN Guo-ying, HAN Shi-quan 5) The establishment of an enzyme linked immunosorbent assay for insulin, No.1, p.24. JIA Juan-juan, LIU Yi-bing, CHEN Jian, XU Wen-ge, GUAN Guo-ying, HAN Shi-quan 99 m 6) Preparation and preliminary evaluation of Tc -HYNIC-β-Ala-BBN（7-14）NH2, No.2, p.77. APPENDIX·List of Scientific Publication in Chinese in 2007 279

QUAN Xin, ZHANG Yan, JIA Bing, SHI Ji-yun, WANG Fan, et al. 7) The experimental measurement of dose field distribution of 125I seed source, No.2, p.98. WANG Xiao-jing, ZHANG Wen-zai, YAO Li-nong, YAN Shu-juan, FENG Xin-zhan, DUAN Li-min, GONG Ling-ling 8) Determination of eighteen trace impurities in tellurium oxide by atomic emission spectrometry, No.2, p.101. ZHAO Xiu-yan, LU Rong, YE Zhao-yun, JIANG Hua, ZHAO Yan 9) The conversion formula on examining shielding effect of the PET special box using 137Cs source as a substitute for 18F, No.2, p.125. LIANG Shi-qiang, YU Tao, et al. 10) Establishment of Immunoradiometric assay for insulin, No.3, p.167. -guang, JIA Juan-juan, LIU Yi-bing, XU Wen-ge 11) New advance on the tracer test technology among wells, No.3, p.189. LIU Tong-jing (CMOE Key Laboratory of Petroleum Engineering, China University of Petroleum), ZHANG Xin-hong, ZHANG Pei-xin, et al. 12) Preparation and evaluation of 177Lu-DOTA-Bz-RGD dimer and 177Lu-DOTA-Bz-PEG4-RGD dimmer, No.4, p.189. SHI Ji-yun, JIA Bing, WANG Fan, et al. 13) On-line wear measurement of an engine using thin layer activation method with charged particles, No.4, p.219. HUANG Dong-hui, WANG Ping-sheng, TIAN Wei-zhi, NI Bang-fa, ZHANG Xiu-hua, LIU Cun-xiong, ZHANG Gui-ying, LI De-hong

39 Journal of Nuclear and Radiochemistry, Vol.29, 2007 1) Study on sub-rapid separation of 91Sr, No.1, p.1. YANG Zhi-hong, DING You-qian, ZHANG Sheng-dong, GUO Jing-ru, CUI An-zhi 2) Fluorimetry of nitrite and its applications, No.1, p.8. QIAN Hong-juan, WU Ji-zong, ZHANG Li-hua, LIU Jun-ling 3) Rate differential kinetic analytical method of Ru3＋ and [RuNO]3＋, No.1, p.15. QIAO Ya-hua, WU Ji-zong 4) Extraction of Am and Eu with iPr-BTP, No.1, p.23. CHENG Qi-fu, YE Guo-an, TANG Hong-bin, JIANG De-xiang, YE Yu-xing, ZHU Zhi-xuan 5) HYNIC-Anx13 labelled with 99Tcm for imaging of apoptosis, No.1, p.32. LI Hong-yu, HU Ji, LIANG Ji-xin, CHEN Bao-jun, LU Jia, LUO Lian-zhe, SHEN Lang-tao, LUO Zhi-fu

6) Reaction kinetics of nitrous acid with acetohydroxamic acid in HClO4 and HNO3 medium, No.3, p.129. ZHENG Wei-fang, YAN Tai-hong, BIAN Xiao-yan, ZHANG Yu 7) Separation of trace plutonium from uranium matrix, No.3, p.135. LI Li-li, LI Jin-ying, ZHAO Yong-gang, ZHANG Ji-long, WANG Tong-xing 8) Synthesis of a novel glycosylated somatostatin and Its 99Tcm radiolabeling, No.3, p.178. HE Chuan, DU Jin, et al. 9) Preparation of micrograms of 173,174Lu, No.4, p.200. DING You-qian, YANG Zhi-hong, MAO Guo-shu, ZHAO Ya-ping, CUI An-zhi, ZHANG Sheng-dong, GUO Jing-ru, SUN Hong-qing, YANG Lei 10) Preparation of uranium target by pulse molecular plating, No.4, p.210. 280 Annual Report of China Institute of Atomic Energy 2007

YANG Chun-li, SU Shu-xin, ZHANG Sheng-dong 11) Synthesis of MAG3-folate and its 99Tcm radiolabeling, No.4, p.231. HU Chun-lin, CUI Hai-ping, DU Jin

40 Nuclear Techniques, Vol.30, 2007 1) Investigation of direct and indirect interaction of DNA damage induced by high LET 7Li ions, No.4, p.250. SUI Li, GUO Ji-yu, KONG Fu-quan, NI Mei-nan, CAI Ming-hui, YANG Ming-jian, LIU Jian-cheng, ZHAO Kui 2) A study of protective action of different scavengers on DNA damage induced by γ rays, No.4, p.255. YANG Ming-jian, KONG Fu-quan, WANG Xiao, NI Mei-nan, SUI Li, CAI Ming-hui, ZHAO Kui 3) Calculation and experimental validation of neutron response for a high sensitivity environmental neutron dose equivalent meter, No.4, p.376. WEI Ying-guang (96411 Unit of PLA), LIU Sen-lin, et al. 4) Synthesis and biological property evaluation of 90Y radiolabeled glycosylated somatostatin, No.5, p.454. ZHAI Shi-zhen (Department of Biophysics, School of Basic Medical Science, Peking University), DU Jin, SHEN Yi-jia, HU Chun-lin, HE Chuan, et al. 5) Monte Carlo computation in the applied research of nuclear technology, No.7, p.597. XU Shu-yan, LIU Bao-jie, et al.

6) Sample preparation of HfF4 for AMS, No.8, p.660. JIANG Tao (Institute of Nuclear Physics and Chemistry; China Academy of Engineering Physics), QIU Jiu-zi, et al. 7) A study on relational ENSDF databases and online services, No.10, p.841. FAN Tie-shuan (Key Lab of Heavy Ion Physics of Ministry of Education, Institute of Heavy Ion Physics, School of Physics, Peking University), HUANG Xiao-long, LIU Tin-jin, et al. 8) Sun bleaching of aluminum center of quartz in cities of different latitudes in China, No.11, p.931. HAN Kong-yan (State Key Laboratory of Earthquake Dynamics, Institute of Geology, China Earthquake Administration), LIN Min, et al. 9) Upgrading the injector system of Beijing HI-13 tandem accelerator, No.12, p.1 001. BAO Yi-wen, GUAN Xia-ling, HU Yue-ming, SU Seng-ying, YOU Qu-bo, HUANG Qing-hua, WANG Xiao-fei, KAN Chao-xin, YANG Tao, FAN Hong-sheng, YANG Bao-jun, LIU De-zhong, YANG Bing-fan, JIANG Shan, HE Ming, LIU Wei-ping, HU Ren-wei, REN Yin, MA Zheng-yu, ZHANG Xiu-hua, YAN Fang, WANG Qiu-ju, LI Ming-long 10) Development of an injection system for a high intensity RFQ, No.12, p.1 008. CUI Bao-qun, MA Yin-jun, LI Li-qiang, MA Rui-gang, JIANG Cong, TANG Bing, WANG Rong-wen, DENG Jin-ting, JIANG Wei-sheng 11) Ion sources for the isotope separator on line in China Advanced Research Reactor, No.12, p.1016. ZHANG Chun-li, ZHU Jia-zheng, QI Bu-jia, YANG Yi, CHENG Pin-jing

41 Journal of Tsinghua University: Science and Technology, 2007 1) Applications of Monte Carlo method in radiation medicine, Suppl. p.907. XU Shu-yan, LIANG Yong, FENG Shu-qiang, LIU Bao-jie, ZHENG Yu-lai 2) Monte Carlo calculations of dose distributions for a 60Co long-distance treatment machine, Suppl. p.914. FENG Shu-qiang, LIU Bao-jie, et al. APPENDIX·List of Scientific Publication in Chinese in 2007 281

3) Ionizing and non-ionizing energy loss of electron and proton for satellite in sun synchronous orbit, Suppl. p.1 013. WANG Chuan-shan (Shanghai Applied Radiation Institute; Shanghai University), HE Xin-fu, et al. 4) Modification and application of SHIELD code, Suppl. p.1 081. TANG Xin-xin (College of Sciences; Shanghai University), FAN Sheng, et al.

42 Electrotechnical Application, Vol.26, 2007 1) Electromagnetic interference analysis and suppression of low-energy high ion-current control system, No.12, p.88. LI Ai-ling, MA Rui-gang, CUI Bao-qun, YANG Bing-fan,

43 Chinese Journal of Nuclear Medicine，Vol.27, 2007 1) Analysis of misdiagnosed solitary pulmonary nodules in lSF-FDG PET/CT imaging, No.3, p.135. ZHENG Jian-guo (Department of Nuclear Medicine, Bering Hospital, Ministry of Health), LUO Zhi-fu, et al.

44 Atomic Energy Science and Technology, Vol.41, 2007 1) Monte-Carlo simulation of cellular S value and specific energy for electrons, No.1, p.14. GENG Jin-peng, CAO Tian-guang, ZHUO Yi-zhong, et al. 2) Calculation of heavy ion beam energy for tandem upgrading project, No.1, p.20. LIU Wei-ping 3) Kinetics of Pu reduction by acetaldoxime and application of acetaldoxime to separation of Pu from U in Purex process , No.1, p.52. HAN Qing-zhen, ZHANG Hu, YE Guo-an, YE Yu-xing 4) RF coupling loop design for superconducting quarter wave resonator, No.1, p.98. PENG Zhao-hua, LU Zhao, GUAN Xia-ling 5) Foundation of experimental system for laser-atomic cluster interaction, No.1, p.101. LI Ye-jun, LU Ze, XI Xiao-feng, YAN Qi-qi, TANG Xiu-zhang 6) Well-type ionization chamber for 192Ir source calibration, No.1, p.113. GUO Wen, WEI Ke-xin, LI Jing-yun 7) Non-destructive assay for uranium standard sample, No.1, p.121. MENG Yan-tai, WANG Xiao-zhong, JIA Xiang-jun, XU Xiao-ming, LI Ze, ZHANG Qi-xin 8) Optimization study on neutronics and self-regulation of cold neutron source for China Advanced Research Reactor, No.2, p.129. SHEN Feng, YUAN Lu-zheng, JIA Zhan-li 9) Substrates texture of Ni-W alloys, No.2, p.137. LI Mei-juan, GOU Cheng, CHEN Dong-feng, LIU Yun-tao 10) Establishment of Enzyme-linked immunosorbent assay for sulfaquinoxaline, No.2, p.142. LIU Chao, LIU Yi-bing, HAN Shi-quan, XU Wen-ge, ZHANG Li-ling 11) Single assembly preliminary analysis for horizontal seismic analysis on fast breeder reactor core, No.2, p.148. WEN Jing, et al. 12) Effect on stability of flyers by altering thickness of ablators, No.2, p.153. LIANG Jing, SHAN Yu-sheng, TANG Xiu-zhang, WANG Zhao, LU Jian-xin 13) Study of (p, γ) reactions on short-lived nuclei using transfer reaction of mirror nuclei, No.2, p.158. 282 Annual Report of China Institute of Atomic Energy 2007

GUO Bing, LI Zhi-hong, LIU Wei-ping, BAI Xi-xiang, LIAN Gang, YAN Sheng-quan, WANG Bao-xiang, SU Jun, WANG You-bao, ZENG Sheng, SHU Neng-huan, CHEN Yong-shou 14) Complete method for cascade correction in gamma-ray measurement, No.2, p.165. LIU Shi-long, YANG Yi, FENG Jing, GUO Xiao-qing 15) Calculation method of absorption efficiency for charged particle emission in silicon detector, No.2, p.169. LIU Wei-ping 16) Sonoluminescence research in water medium, No.2, p.177. BAO Jie, LIU Yong-hui, HUANG Han-xiong, ZHOU Zu-ying, TANG Hong-qing 17) Element composition analysis of airborne particulate matter (PM10 and PM2.5) by Instrument Neutron Activation Analysis, No.2, p.228. YANG Wei-tao, NI Bang-fa, WANG Ping-sheng, TIAN Wei-zhi, SHEN Li, XIAO Cai-jin, ZHANG Gui-ying, LIU Cun-xiong, HUANG Dong-hui, HU Lian, LU Peng 18) Non-destructive assay for segmented gamma scanning calibration standards, No.2, p.248. HE Li-xia, LU Feng, ZHAO Xue-jun, SUI Hong-zhi, LIU Heng-jun, LI Ze 19) Hard X-ray Energy spectrum on ultrashort pulse laser interaction with solid target, No.3, p.257. YAN Qi-qi, WANG Nai-yan, SHAN Yu-sheng, LI Ye-jun, TANG Xiu-zhang 20) Establishment of monoenergetic neutron reference radiation fields from 0. 144 to 1.2 MeV, No.3, p.262. CHEN Jun, WANG Zhi-qiang, LIU Yi-na, LUO Hai-long 21) Development of 350 keV electron accelerator, No.3, p.273. QIN Jiu-chang, CUI Shan, ZHOU Wen-zhen, CUI Zhi-peng, SHI Zheng-hu, LU Zhong-cheng, et al. 22) Theoretical calculations for n＋58,60 Ni reactions, No.3, p.278. HAN Jian (Department of Physics, Northwest University), HAN Yin-lu, et al. 23) Research on radiological consequences of severe accident of china advanced research reactor, No.3, p.331. ZHANG Hai-xia, LIU Sen-lin, JIANG Xi-wen 24) High precision measurement of decay rate of 7Be in Au, No.4, p.408. MENG Qiu-ying, LI Cheng-bo, FU Yuan-yong, LIU Zhi-yi, WEN Qun-gang, ZHOU Jing, ZHOU Shu-hua 25) Sensitivity curve measurement and application of radioactivity meter, No.4, p.480. YAO Shun-he, WANG Jian-qing, GUO Xiao-qing, YAO Yan-ling 26) Equipment to measure cha e distributions of fragments low energy fission, No.4, p.484. WANG Tao-feng, MENG Qing-hua, WANG Li-ming, ZHU Li-ping, HAN Hong-yin, XIA Hai-hong 27) Production of 13N secondary beam, No.5, p.513. ZENG Sheng, LI Zhi-hong, LIAN Gang, WANG You-bao, SU Jun, YAN Sheng-quan, WANG Bao-xiang, GUO Bing, BAI Xi-xiang, LIU Wei-ping 28) A portable hydrogenator for in-situ neutron scattering measurements, No.5, p.517. YUAN Xue-zhong (Chinese Academy of Sciences), SUN Kai, CHEN Dong-feng, et al. 29) Accurate and precise determination of small qantity uanium by means of automatic potentiometric titration, No.5, p.546. LIU Quan-wei, LUO Zhong-yan, ZHU Hai-qiao, WU Ji-zong 30) Thermal stratification phenomenon in pipelines of nuclear power plant, No.5, p.570. GUO De-peng (North China Electric Power University), FENG Yu-heng, et al. 31) Estimation of transverse shielding for intense-beam proton linac, No.5, p.610. GUO Wen, ZHAO Zhi-xiang, et al. 2 4 32) H(d, γ) He reaction cross section at Ed = 20 keV, No.6, p.663. APPENDIX·List of Scientific Publication in Chinese in 2007 283

ZHOU Jing, FU Yuan-yong, XIA Hai-hong, ZHOU Shu-hua 33) Energy Re-calibration of HI-13 tandem accelerator, No.6, p.668. LI Zhi-chang, ZHAO Kui, LU Xiu-qin, GUO Ji-yu, CHEN Quan, GUO Gang, LIU Jian-cheng, SHEN Dong-jun, SUI Li, HUI Ning, KONG Fu-quan, CAI Ming-hui, YANG Ming-jian, HU Yue-ming, BAO Yi-wen 34) Application of Monte-Carlo method in multi-telescope system based on cylindrical multi-wire proportional chamber, No.6, p.674. CHENG Pin-jing (School of Nuclear Science and Technology, University of South China), RUAN Xi-chao, ZHOU Zu-ying, JIANG Jing, LI Xia, HUANG Han-xiong, TANG Hong-qing 35) Small angle-rotated detector emission tomography for measuring holdup in spherical container, No.6, p.742. DENG Jing-shan (The Fifth Research and Design Institute of Nuclear Industry), LI Ze, GAN Lin, LU Wen-guang, DONG Ming-li 36) Preliminary design of lead-bismuth eutectic thermalhydraulic and corrosion test loop, Suppl., p.27. QIAN Yan-yue 37) Simulation of flow transients characteristics of sodium/argon flow in anti-siphon equipment’s curve pipeline of China experimental fast reactor, Suppl., p.79. PENG Yan, ZHANG Dong-hui 38) An assessment of critical flow model in RELAP5, Suppl., p.162. CHEN Yu-zhou, YANG Chun-sheng 39) Numerical analysis of thermal stratification in upper plenum of “Monju” fast reactor by using STAR-CD code, Suppl., p.167. XU Yi-jun, HOU Zhi-feng, ZUE Xiu-li, FENG Yu-heng, QIAO Xue-dong 40) Numerical study on thermal-hydraulics in in-hospital neutron irradiator, Suppl., p.196. MAO Yu-long, ZHAO Ai-hu, CHEN Yu-zhou 41) Three-dimention numerical simulation of whole core composed heat sodium pool for China experimental fast reactor, Suppl., p.201. FENG Yu-heng, QIAO Xue-dong 42) Numerical analysis of distribution header and primary loop pressure tube for China experimental fast reactor, Suppl., p.208. FENG Yu-heng, QIAO Xue-dong 43) Numerical simulation of immersion cooler for China experimental fast reactor, Suppl., p.213. FENG Yu-heng, QIAO Xue-dong 44) Development and analysis of radiator’s thermal-hydraulic calculation program, Suppl., p.217. GUO Chun-qiu, HAO Lao-mi 45) China experimental fast reactor fault tree analysis of cooling water system of nuclear-related equipment, Suppl., p.223. SONG Wei, YANG Hong-yi 46) Probabilistic safety analysis of sodium fire in reactor hall of China experimental fast reactor, Suppl., p.227． QIAN Hong-tao 47) Numerical simulation of flow and temperature field of fuel subassembly for China experimental fast reactor, Suppl., p.230. LIU Yi-zhe, YU Hong 48) Accident analysis on ATWS of China advanced research reactor, Suppl., p.276. TIAN Wen-xi (State Key Laboratory on Power Engineering and Multiphase Flow, Department of 284 Annual Report of China Institute of Atomic Energy 2007

Nuclear & Thermal Power engineering, Xi’an Jiaotong University), ZHANG Jian-wei, et al. 49) ASTEC V1.2 CPA & IODE analysis on severe accident source term, Suppl., p.294. HUANG Dong-xing, et al. 50) Analysis on China advanced research reactor high-temperature and high-pressure loop SBIOCA, Suppl., p.302. ZHANG Yi, ZHANG Ying-chao, JI Song-tao 51) Sodium spray fire calculation and analysis of sodium decontaminated system of first loop of China experimental fast reactor, Suppl., p.306. HU Wen-jun, YU Hong 52) Accident analysis of total instantaneous blockage of a fuel subassembly at nominal power of China experimental fast reactor, Suppl., p.310. REN Li-xia 53) Study on corrosion behavior of new Zr-Nb alloy, Suppl., p.342. WANG Hui, HU Shi-lin, YANG Qi-fa, ZHANG Ping-zhu, et al. 54) Test for mechanical properties on 6061-T6 Aluminium of China advanced research reactor, Suppl., p.357. NING Guang-sheng, XU Yuan-chao, TONG Zhen-feng, ZHANG Chang-yi, LIN Hu, YANG Wen 55) Microstructure analysis of alloying Mo-3Nb single crystal materials, Suppl., p.361. ZHENG Jian-ping, YANG Qi-fa, WU Wei

56) Study on technology of high temperature brazing of Nb-1Zr and 1Cr18Ni9Ti in vacuum, Suppl., p.365. QI Li-jun, CAI Hong-tao 57) Stress concentration and constraint force influencing electron beam welding of Mo-3Nb monocrystal alloy, Suppl., p.370. LI Xin 58) Development of TransTemp program for analysis of reactor pressure vessel irradiation surveillance data, Suppl., p.374. LIN Hu, ZHANG Chang-yi, NING Guang-sheng, TONG Zhen-feng, XU Yuan-chao, YANG Wen 59) Research and development status of China liquid Li-Pb blanket materials, Suppl., p.397. HUANG Qun-ying (Institute of Plasma Physics, Chinese Academy of Sciences), YU Jin-nan, ZHU Sheng-yun, ZHANG Pin-yuan, et al.

45 China Nuclear Science and Technology Report，2007 1) Studey on a new calibration methods of in-situ HPGe γ spectrometers used for non-destructive analyzing radioactivity in nuclear facilities decommissioning, CNIC-01893, IAE-0221. XIAO Xue-fu, SONG Li-jun, WANG Yu-lai, WEN Fu-ping, LIAO Hai-tao, BAN Ying, XIA Yi-hua, LI Rui-xiang, LI Hang, TU Xing-min 2) The research of removing sodium aerosol, CNIC-01896, IAE-0222. YU Xiao-chen, HONG Shun-zhang, CAO Zen, WU Jie, ZHAGN Xiu-feng 3) Chemiluminescence immunoassay for chloramphenicol, CNIC-01904, IAE-0223. LIN Si, XU Wen-ge, LIU Yi-bing 4) Time-resolved immunofluorometric assay of serum ferritin, CNIC-01905, IAE-0224. YAO Yan 5) Review: Microspheres for radioembolization therapy, CNIC-01918,IAE-0225. ZHAO Ming-qiang, XU Shu-he APPENDIX·List of Lectures in International Meetings in 2007 285

List of Lectures in International Meetings in 2007

No. Report title Meeting title Time and place Reporter 1 Survival and genomic 2006 Annual Report of the Biology, Chiba, WANG Xiao, et instability in mutation Research Project with heavy Japan al. induction on long-term ions at NIRS-HIMAC cells cultures irradiated with heavy ions 2 Integral test of natural 2007 International Conferen- France, April, 2007 LIU Ping tungsten for CENDL-3.1 ce on Nuclear Data 3 Introduction on the IAEA/RCA Regional 2007.02.26-03.02, HAN Song-bai neutron scattering Training Course on Korea Advanced Neutron Beam Technology & Application in Korea 4 Neutron scattering at IAEA/RCA Regional 2007.02.26-03.02, LI Mei-juan CARR Training Course on Korea Advanced Neutron Beam Technology & Application in Korea 5 Low activation ferritic/ 3rd International Symposium 2007.03.12-15, LI Huai-lin martensitic steel, poten- on Supercritical Water- China, Shanghai tial core structure cooled Reactors （ SCWR material of supercritical 2007） water cooled reactor 6 Evaluation of the decay The Second Co-ordination 2007.03, 28-30, HUANG data of Ac-225 Meeting(RCM) on Updated Vienna, Austria Xiao-long Decay Data Library for Actinides 7 Evaluation of the decay The Second Co-ordination 2007.03, 28-30, HUANG data of Bi-213 Meeting(RCM) on Updated Vienna, Austria Xiao-long Decay Data Library for Actinides 8 Investigation of DNA China-Korea Joint Sympo- 2007.04，China, ZHAO Kui damage induced by sium on Nuclear Technique high LET 7Li ions Application in Agriculture and Life Science 9 Present status of Meeting of the OECD/NEA 2007.04.19-20, YU Hong-wei CENDL project Working Party on Interna- Issy-les-Moulincaux, tional Nuclear Data Evalua- France tion 10 The updated version of The 2007 International 2007.04.20-28, Nice, YU Hong-wei Chinese evaluated Conference on Nuclear France nuclear data library Data for Science and (CENDL-3.1) and Technology China nuclear data evaluation activities 286 Annual Report of China Institute of Atomic Energy 2007

11 Two-proton halo and International Nuclear 2007.06.03-08, LIN Cheng-jian two-proton emission Physics Conference Tokyo, Japan nucleus: 29S 12 Microscopic optical International Symposium 2007.06. 11-15 MA Zhong-yu potentials of nucleon- on Exotic States of Catania, Italy, June nucleus and nucleus- Nuclear Matter 2007 nucleus scattering 13 Status report of the Co-ordination of the 2007.06.11-15, HUANG Xiao- nuclear structure and International Network of Russian, Federation, long, WU Zhen- decay data evaluation Nuclear Structure and dong in CNDC decay Data Evaluators, St.Petersburg 14 Two-proton halo and International Conference on 2007.06.17-23, LIN Cheng-jian Two-proton emission Proton Emitting Nuclei and Lisbon, Portugal Nucleus:29S Related Topics 15 Performance analysis of 15th Session of Internation- 2007.04.22-26, HUANG Chen

B4C used as shielding al Nuclear Engineering Japan material in China Congress (ICONE-15) experimental 16 Mechanical properties 15th Session of Internation- 2007.04.22-26, YANG Wen of SiC nanowires/fibers al Nuclear Engineering Japan reinforced SiC matrix Congress (ICONE-15) composites 17 Highlights of fuel IAEA-TWGFPT Technical 2007.04.24-26, JI Song-tao research in China Meeting Vienna 18 Design & construction International Conference on 2007.06.24-29, ZHANG Tian- status of CYCIAE-100. Electromagnetic Isotope Deaveaulli, France jue a 100 MeV H-cyclotron Separators and Techniques for RIB production Related to Their Application (Emis2007) 19 The transfer beam line International Conference on 2007.06.24-29, WEI Su-min design after stripping Electromagnetic Isotope Deaveaulli, France extraction for the Separators and Techniques CYCIAE-100 Related to Their Application (Emis2007) 20 Microscopic optical International Symposium 2007.07.03-07, MA Zhong-yu potential in relativistic on Physics of Unstable Vietnam approach Nuclei 21 A new pairing force for International Symposium 2007.07.03-07, TIAN Yuan relativistic hartree on Physics of Unstable Vietnam bogoliubov calculations Nuclei in static and dynamic aspects of exotic nuclei 22 The study of continuum International Symposium 2007.07.03-07, YANG Ding relativistic random on Physics of Unstable Vietnam phase of approximation Nuclei 23 The study of dynamical International Workshop on 2007.07.09-14, LI Zhu-xia isospin effects on Nuclear Dynamics in Beijing, China reactions of p+112-132Sn Heavy-ion Reactions and APPENDIX·List of Lectures in International Meetings in 2007 287

Neutron Stars 24 Inner crust of neutron International Workshop on 2007.07.09-14, CAO Ji-guang stars in a relativistic Nuclear Dynamics in Beijing, China mean field approach Heavy-ion Reactions and Neutron Stars 25 One single horizontal The Transactions of 19th 2007.08.12-17, WEN Jing, et al. seismic analysis of International Conference of Canada FBR core Structural Mechanicals in Reactor Technology 26 Gauge symmetry and International Workshop on 2007.08.14-15, HE Han-xin transverse symmetry Dyson-Schwinger Eguation Beijing, China transformations in and its Applications gauge theories 27 Multi-goal control of The Fourth Asia-Pacific 2007.08.24-26, FANG Jin-qing, halo chaos in beam Workshop on Chaos Harbin, China et al. transport networks with Control and Synchroniza- small-world and scale- tion free 28 Design of changeable The Fourth Asia-Pacific 2007.08.24-26, ZHAO Geng, P-box and two modules Workshop on Chaos Harbin, China FANG Jin-qing, structure in block Control and Synchroniza- et al. cryptosystem based on tion chaos 29 Ion source and low The 12th International 2007.08.26-31, ZHANG Tian- energy injection line for conference on Ion Sources Korea jue a CRM cyclotron (ICIS2007) 30 Matching from The 12th International 2007.08.26-31, YAO Hong-juan H-multicusp source to conference on Ion Sources Korea central region of a 100 (ICIS2007) MeV compact cyclotron for high current injection 31 China’s radioactive International Experience in 2007.09.17-19, ZHANG Zhen- wastes and the scaling the Determination and Use Vienna tao factor method of Scaling Factors in Waste Characterization 32 Triple-axis spectro- The First CARR-NSL 2007.09.21-22, WU Zhan-hua meter and four-circle International Advisary Beijing, China diffractiometer: a rela- Committee Meeting tion project 33 An overview of the The First CARR-NSL 2007.09.21-22, CHEN neutron scattering International Advisary Beijing, China Dong-feng project at NSL-CARR Committee Meeting 34 Evaluation of novel Seventh Session of 2007.09.26-30, DENG Xin-rong neropnsin analogue Radioactive Pharmaceutical Japan 125I-NTx Chemistry Seminar 35 HYNIC-Anx13 labelled Seventh Session of 2007.09.26-30, LI Hong-yu with 99mTc for Radioactive Pharmaceutical Japan imaging of apoptosis Chemistry Seminar 36 Design and construc- 18th Session of Interna- 2007.09.30-10.05, ZHANG 288 Annual Report of China Institute of Atomic Energy 2007

tion progress of tional Cyclotron Congress Giardini Naxos, Italy Tian-jue CYCIAE-100. a 100 (ICC2007) MeV H-Cyclotron at CIAE 37 Extraction simulation 18th Session of Interna- 2007.09.30-10.05, AN Shi-zhong for CYCIAE-100 tional Cyclotron Congress Giardini Naxos, Italy (ICC2007) 38 Test beam line for 18th Session of Interna- 2007.09.30-10.05, AN Shi-zhong pulsed beam generation tional Cyclotron Congress Giardini Naxos, Italy at CIAEs CRM (ICC2007) cyclotron 39 The study and design of 18th Session of Interna- 2007.09.30-10.05, YAO Hong-juan spiral inflector and tional Cyclotron Congress Giardini Naxos, Italy central region for (ICC2007) CYCIAE-100 cyclotron 40 Gap-crossing resonance 18th Session of Interna- 2007.09.30-10.05, YAO Hong-juan in CYCIAE-100 tional Cyclotron Congress Giardini Naxos, Italy cyclotron (ICC2007) 41 Investigation of intense 18th Session of Interna- 2007.09.30-10.05, YANG Jian-jun beam transport on tional Cyclotron Congress Giardini Naxos, Italy injection line and (ICC2007) inflector of compact cyclotron 42 Thermal analysis of RF 18th Session of Interna- 2007.09.30-10.05, WEI Su-min cavity for CYCIAE-100 tional Cyclotron Congress Giardini Naxos, Italy (ICC2007) 43 Study on space charge 18th Session of Interna- 2007.09.30-10.05, JIA Xian-lu effect in the spiral tional Cyclotron Congress Giardini Naxos, Italy inflector (ICC2007) 44 The study on RF cavity 18th Session of Interna- 2007.09.30-10.05, BI Yuan-jie tolerance for tional Cyclotron Congress Giardini Naxos, Italy CYCIAE-100 (ICC2007) 45 Steps forward in the 18th Session of Interna- 2007.09.30-10.05, YIN Zhi-guo digital RF control tional Cyclotron Congress Giardini Naxos, Italy system at INFN-LNS (ICC2007) 46 Dynamics intermediate The Third Session of 2007.10.14-16, ZHUO Yi-zhong between Newton and International Physical, Xinjiang, China Langevin－The role of Chemistry and Biological environments Interdisciplinary Studies Seminar (Chinese Xinjiang Shihezi CJCSS-4 Seminar) 47 The DNA concentration The Third Session of 2007.10.14-16, ZHAO Kui and dose rate effects on International Physical, Xinjiang, China DNA radiation damage Chemistry and Biological induced by heavy ions Interdisciplinary Studies Seminar (Chinese Xinjiang Shihezi CJCSS-4 Seminar) 48 Observation of 3He and 8th International Workshop JIANG 3H in the volcanic on Anomalies in Song-sheng APPENDIX·List of Lectures in International Meetings in 2007 289

crater lakes: possible Hydrogen/Deuterium evidence for natural Loaded Metals nuclear fusion in deep earth 49 Controlling reactor Second Session of 2007.10.15-16, ZENG Hai power of CARR with a Intelligent System and , China fussy logic controller Knowledge Engineering International Conference 50 Genomic mutation The 6th International 2007.10.18-20, WANG Xiao study for Long-Term Conference on Low dose Budapest cells induced by carbon Radiation Effects on ions Human Health and Environment 51 10Be measurement Second Session of East 2007.10.21-24, HE Ming method and its Asian AMS Conference Korea applications in CIAE 52 41Ca measurement and Second Session of East 2007.10.21-24, JIANG Shan it’s applications in Asian AMS Conference Korea biology 53 China ADS study in Asian Network on 2007.11.01-03, XIA Hai-hong Phase 2 Innovative Nuclear Systems Korea Embedding 5th Wrokshop of Asian ADS 54 Current status of SLND “Uses in the Advanced Post 2007.11.12-16, LI Hong-yu and CD using 99mTc Lymph Node Examination Vienna, Austria radiopharmacen- ticals and the Tumor Developing in CIAE 99mTc Radioactive Medicine Development” the CRP Project First Coordination Meeting 55 Global alpha optical The Third Research Co- 2007.12.10, HAN Yin-lu potential parameters at ordination Meeting of the Vienna, Austria energies up to 200 MeV International Atomic energy Agency’s Co-ordinated Re- search Project on “Parameters for Calculation of Nuclear Reactions of Relevance to Non-energy Nuclear Applications” (RIPL-3) 56 The validation of RIPL The Third Research Co- 2007.12.10, HAN Yin-lu II for n+238U reaction ordination Meeting of the Vienna, Austria International Atomic energy Agency’s Co-ordinated Re- search Project on “Parameters for Calculation of Nuclear Reactions of Relevance to Non-energy Nuclear Applications” (RIPL-3) 57 Global and local The Third Research Co- 2007.12.10, HAN Yin-lu 290 Annual Report of China Institute of Atomic Energy 2007

deuteron optical ordination Meeting of the Vienna, Austria potential parameters at International Atomic energy energies up to 200 MeV Agency’s Co-ordinated Re- search Project on “Parameters for Calculation of Nuclear Reactions of Relevance to Non-energy Nuclear Applications” (RIPL-3) 58 The validation of RIPL The Third Research Co- 2007.12.10, HAN Yin-lu II for n, p+54, 56Fe ordination Meeting of the Vienna, Austria reaction International Atomic energy Agency’s Co-ordinated Re- search Project on “Parameters for Calculation of Nuclear Reactions of Relevance to Non-energy Nuclear Applications” (RIPL-3) 59 The status repot for The Third Research Co- 2007.12.10, HAN Yin-lu 12842/R ordination Meeting of the Vienna, Austria International Atomic energy Agency’s Co-ordinated Re- search Project on “Parameters for Calculation of Nuclear Reactions of Relevance to Non-energy Nuclear Applications” (RIPL-3) 60 Fatigue life and strain The 13th Session of Fusion 2007.12.10-14, LI Huai-lin hardening behavior of Piles the Material Nice, France JLF-1 steel Conference (ICFRM-13) 61 Views and thoughts on 4th Asian Regional 2007.12.13-14 XIA Yi-hua the evolution of system conference on the Evolution of radiological of the System of protection Radiological Protection 62 An assessment of Proc. 3rd Int. symposium CHEN Yu-zhou, critical flow modes in on SCWR design and Tech- YANG Chun- RELAPS nology (SCR2007-P055 sheng Plenary Lectures) 63 Assessments of Proc. the 3rd Sino-Korea RELAPS models in Workshop on Nuclear CIAE Reactor Thermal-Hydrau- lics