CN9800570 CNIC-01169

CHINA NUCLEAR SCIENCE AND TECHNOLOGY REPORT ffi

ABSTRACTS 1996

4* H tt « m =5- m til Kg %h China Nuclear Information Centre Atomic Energy Press ABSTRACTS CHINA NUCLEAR SCIENCE & TECHNOLOGY REPORT (1996) ABSTRACT

The bibliographies and abstracts of China Nuclear Science and Technology Re- ports published in 1996 (Report Numbers CNIC-01021 —CNIC-01130) are pre- sented. The items are arranged according to INIS subject categories, which mainly are physical sciences, chemistry, materials, earth sciences, life sciences, isotopes, isotope and radiation applications engineering and technology, and other aspects of nuclear energy. The numbers on the left corners of the entries are report numbers, and on the right corners the serial numbers. A report number index is annexed. TABLE OF CONTENTS

A00.00 fyWfti$ PHYSICAL SCIENCES A10.00 ^iitlil^ GENERAL PHYSICS (1) A30. 00 ^^^SM^^^^jM^ NEUTRON AND NUCLEAR PHYSICS (10) B00.00 tt^, **#-5Jfti#f4^ CHEMISTRY, MATERIALS AND EARTH SCIENCES B10. 00 ik¥ CHEMISTRY (13) B20.00 $•£)• MATERIALS (23) B30.00 ifej*^ EARTH SCIENCES (32) C00 00 ±$>&!£ LIFE SCIENCES C10.00 ±t|^^h$ltM0f:t%l£.X&flIl5lJ@ ALL EFFECTS AND VARI- OUS ASPECTS OF EXTERNAL RADIATION IN BIOLOGY (43) C20. 00 mN&W\&m±&R$]Jl¥ RADIOISOTOPE EFFECTS AND KINETICS • (44) C40. 00 &$

PHYSICAL SCIENCES

AIO. oo ^M^a^

GENERAL PHYSICS

A12.00 Atomic and Molecular Physics

CNIC-01059 960001 IAE-0151 "CottCTrft/a.u^oft-RfflaESEKWK/S M P W fiSM

m Q3D flUtiX^^, ^ HI-13 $?lJMff£|#t#J 35 MeV a T5fFe (a, d) 5"Co

6.4

EXPERIMENT STUDY OF THE (ir g9/2, u g9/2) STRETCHED CONFIGURA- TION IN 58Co /YUAN Jian LU Ming et al. (China Institute of Atomic Ener- gy, ) (In Chinese) The interest of the search for the stretched state stems largely from the fact that these states are usually considered to be of fairly pure nuclear shell model con- figuration and often used to help define the appropriate configuration space, deter- mine the proper residual interaction in the multi-particle shell model calculation and provide a good wave function for study of three nucleon transfer reaction with fully microscopic DWBA analyses. Actually, only a few pure shell model configurations have been observed in some light nuclei so far. One intends to search for the exis- tence of the stretched state in medium mass. The fine spectra and the angular distri- 1 butions of differential cross-section strongly excited by 35 MeV a ion bombardment in 56Fe(a,d)58Co reaction in HI-13 Tandem Accelerater in terms of AE-E telescope and Beijing Q3D magnetic spectrometer have been measured. The stretched state + for 6- 79 MeV 9 with the highest in gg/2, u g9/2) configuration was identified and the 6- 4 MeV high-lying level was newly assigned to be 1+ state in 58Co.

A13.00 Solid State and Fluid Physics

CNIC-01107 960002 ZZU-0002

1250'C (2) 3+ (Fe2O3. Fe ) (SJ2)

1200 C , (YJ3)

APPLIED INVESTIGATION OF MoSSBAUER EFFECT FOR THE FAMOUS ANCIENT CHINESE PORCELAINS/GAO Zhengyao CHEN Zuocheng ( Zhengzhou University ), SHEN Zuocheng ( Zhengzhou Institute of Light Industry) The famous Ru porcelain, Jun porcelain and Guan porcelain of Song Dynasty and Yuan Dynasty are analyzed. The Mossbauer parameters of the ancient porce- lains and the imitative ancient porcelains are compared. The firing techniques, color- ing mechanism and microstructures of the ancient Chinese porcelains have been dis- cussed. The results are shown as follows: (1) The Ru poreclain glaze contain struc- 2+ 3+ ture iron (Fe ,Fe ) and magnetic component Fe3O4. The original firing tempera- tures of Ru porcelain of Yuan Dynasty and Song Dynasty are inferrd to be 1250 C • The original firing atmospheres are determined to be reductive. The glaze color of the Ru porcelain is related to the chemical state of iron. (2) The ancient Jun 2+ porcelain glazes contain iron minerals (Fe2O3, Fe3O4) and structural iron (Fe , 2 Fe3+) entered clay mineral lattice. The original firing temperature of Jun porcelain

(SJ2) of Song Dynasty is determined to be above 1200 °C » the original firing tem- perature of Jun porcelain (YJ3) of Yuan Dynasty is a little higher than 1250 C- The firing atmosphere of sky-blue Jun porcelain of Song Dynasty is strongly reduc- tive atmosphere. The firing atmosphere of sky-green Jun porcelain of Song Dynasty and the imitative ancient blue Jun porcelain is modestly reductive atmosphere. The firing atmosphere of moon-white Jun porcelain of Yuan Dynasty is weak reductive atmosphere. The coordination numbers of both Fe2+ and Fe3+ are 4. The coloring mechanism of Jun porcelain is very complex. Iron is only one of the major colorant in Jun porcelain. The chemical state of iron is only one of factors that influence the glaze color of Jun porcelain. (3) The glaze color of Southern Song Guan porcelain is related to the chemical state of iron. The more structure iron content is contained in powder-green glaze as well as greyish-green glaze. The more ferric oxide content is contained in cream-yellow glaze. The firing atmosphere of powder-green glaze and greyisb-green glaze is strongly reductive atmosphere, the cream-yellow glaze is to be weak reductive atmosphere. The firing temperature of the former is higher than the later.

Ai4.oo Plasma Physics and Thermonuclear Reactions

CNIC-01054 960003 ASIPP-0046 ffl%*»A#J*£«nTgto L-H «$$»/» fi

ffl

THE CONTROLLABLE L-H TRANSITION REALIZED BY INJECTION OF ELECTRONS/PAN Yuan WANG Maoquan MAO Jianshan et al. (Institute of Plasma Physics, Academia Sinica. Hefei) A new way to get and control H mode is proposed. Theoretic analysis and cal- culation show that the electron injection by pulsed EXB drift can trigger the H mode without direct contact with plasma and could realize the feedback control for the H mode. A repeatable pulsed field and electron beam system with a frequency of 1 kHz that has been demonstrated enough for HT-6M Tokamak experiment are 3 given in detail.

CNIC-01026 960004 SIP-0088

2.45 m (XPS), £j*££*rasiH-$»S:*hfti» CATR-FTIR)

MICROWAVE PLASMA INITIATED GRAFT COPOLYMERIZATION MODI- FICATION OF MONOMERS ONTO PTFE SURFACE/GUAN Weishu WEN Yunjian FANG Yan et al. (Southwestern Institute of Physics, Chengdu) A graft copolymerization modification technique of monomers onto polyte- trafluoroethylene (PTFE) surface initiated by a 2-45 GHz non-equilibrium mi- crowave plasma has been investigated. Standard X-Ray Photoelectron Spectroscopy (XPS), Attenuated Total Reflectance-Fourier Transform Infrared Spectroscopy (ATR-FTIR) , Scanning Electron Microscopy (SEM) and wetting techniques were used for examination and analysis of samples. Considerable changes in chemical structure, composition and in morphology of grafted surface of PTFE were found. Results showed the occurrence of noticeable defluorination and cross-linked struc- ture on grafted surface, and indicated that different kinds and contents of oxygen- containing functional groups were introduced into the surface of PTFE. Wetting and adhesion experiment of the sample proved that significant improvements in hy- drophilicity and adhesion of surface were exhibited. These results confirmed the success of grafting.

CNIC-01034 960005 ASIPP-0045

NUMERICAL SIMULATION OF EDGE PLASMA IN TOKAMAK/CHEN Yip- 4 ing QIU Lijian (Institute of Plasma Physics, Academia Sinica, Hefei), LUAN Guishi (Da Heng Company, Academia Sinica, Beijing) The transport process and transport property of plasma in edge layer of Toka- mak are simulated by solving numerically two-dimensional and multi-fluid plasma transport equations using suitable simulation code. The simulation results can show plasma parameter distribution characteristics in the area of edge layer, especially the characteristics near the first wall and divertor target plate. The simulation re- sults play an important role in the design of divertor and first wall of Tokamak.

CNIC-01051 960006 HL-2

0. 22 A • cm-2ft 0. 155 A • cm"2, DESIGN CALCULATION OF THE ION BEAM SYSTEM FOR HL-2 NEUTRAL BEAM INJECTOR/WANG Huisan JIAN Guangde JIANG Shaofeng (South- western Institute of Physics, Chengdu) (In Chinese} In fusion research, the neutral beam injection has become an efficient method for heating plasma. A key part of the neutral beam injector is ion beam system, whose property defines the efficiency and effect of the neutral beam injector. De- sign calculation method about main work parameters of the ion source and the ion extraction-acceleration system for high power neutral beam injectors are described and the calculated results of the ion beam system for HL-2 neutral beam injector are given. In the numerical calculation code about optical property of the high cur- rent ion beam extraction-acceleration systems, the effects of ion source plasma pa- rameters, plasma stray electron and space charge effect inside the ion beam on beam optical property are taken into account. The calculation shows for the deter- minate 55 keV,80 A ion beam systems, the match current densities of H and D ion beams are 0. 22 A • cm"2 and 0. 155 A • cm"2, respectively. CNIC-01064 960007 sip-0091

«M*«c*CiSl8.9mg/L, Jifli/^QnTi* 1800 mg/h, JMWMB/** 7 * 70 g/ (kW

•h) (ffl^Tm^tg^^,»14kW.h/kg! ftW^Mfi^llif L, Q=730mg/h, 7=31 g/ (kW • h) (P,= 32 kW • h/kg), fiC, Q

85%, EXPERIMENTAL INVESTIGATION ON SYNTHESIS OF OZONE IN NON-E- QUILIBRIUM OXYGEN PLASMA AND ITS APPLICATION/DU AN Shuyun CHENG Shiqing XIA Hua et al. (Southwestern Institute of Physics, Chengdu) (In Chinese) The synthesis of ozone in non-equilibrium oxygen plasma is performed by us- ing silent discharge method. When oxygen is used as discharge gas, the mass con- centration of ozone C is 18-9 mg/L and production rate Q is 1800 mg/h, specific energy rate y is 70 g/ (kW • h). When discharge takes place in the air, the results obtained are: C=12 mg/L, Q = 730 mg/h, 7=31 g/ (kW • h). The mass concen- tration of ozone rises with the increase of voltage applied on the electrodes and re- duces following the increase of the gas flow rate. But the production rate of ozone rises with the increase of the gas flow rate slightly. The properties of the dielectric material and its thickness will influence the performance of the ozonizer strongly. It is found that raising the frequency of the high voltage power source and using a square wave high voltage can improve the performance of the ozonizer as well. The experimental investigation results show that: ozone can be used in disposal of pulp waste liquor because of its strong oxidizing ability. The effect of decolour is ob- served and ageing stability is very well and no recolour phenomenon appears after being treated and laying aside for 118 days. Both effects of reducing the viscosity and removing the lignin are obtained as well.

CNIC-01082 960008 SIP-0092 G • LeClair Hazeltine

EFFECTS OF RADIAL ELECTRICAL FIELD ON NEOCLASSICAL TRANS- PORT IN TOKAMAKS/WANG Zhongtian (Southwestern Institute of Physics, Chengdu) G • Le Clair (Canada Fusion Centre) Neoclassical transport theory for tokamaks in the presence of a radial electrical field with shear is developed using Hamiltonian formalism. Diffusion coefficients are derived in both plateau regime including a large electric field and banana regime in- cluding the squeezing factor which can greatly affect diffusion at the plasma edge. The scaling on squeezing factor is different from the one given by Shaing and Hazeltine. Rotation speeds are calculated in the scrape-off region. They are in good agreement with measurements on TdeV Tokamak.

CNIC-01090 960009 SIP-0093

t RFP

, RFP

100

PLASMA TOROIDAL VOLTAGE AND CURRENT MEASUREMENTS ON SWIP-RFP DEVICE/LI Qiang ZHANG Peng LUO Cuiwen (Southwestern In- stitute of Physics, Chengdu) The plasma toroidal voltage and toroidal current measurement methods and some results on SWIP-RFP device are presented. The preliminary model for the toroidal voltage of an RFP plasma is analyzed. The toroidal voltage measured with an one turn coil depends largely on the external current, i. e. there is an inducted component in the one turn coil voltage. Even though the inducted component is tak- en into account, the plasma toroidal voltage for an RFP plasma exceeds the classical resistive toroidal voltage for a toroidally driven system, this is an interesting subject related to the plasma helicity balance for an RFP plasma. The electromagnetic fea- 7 tures related to the toroidal voltage measurement are studied. The experiments show that the plasma current is above 60 kA normally, with better discharge condi- tions, the plasma current can be driven to 100 kA. The one turn coil voltage is about 250 V with maximum plasma current during a discharge. These results are consistent with the estimated results via other signals, furthermore, high plasma current density and the existence of anomalous toroidal voltage for the RFP plasma are revealed.

CNIC-01093 960010 SIP-0094 g%%«m ULQ

ULQ

EXPERIMENTAL STUDY OF ULTRA LOW Q PLASMA WITH HIGH CUR- RENT DENSITY/ZHANG Peng LI Qiang LUO Cuiwen et al. (Southwestern Institute of Physics, Chengdu) Ultra Low q (ULQ) experimental results with high current density are given. ULQ plasma with fine confinement and high temperature is obtained after wall car- bonization and siliconization. Dynamo effect caused long-period enhancement of toroidal magnetic field, anomalous resistivity and anomalous ion heating are ob- served. A similar Isotope effect is also observed in discharges with different filling

gases [He+H2 + SiH< or H2].

CNIC-01117 960011 SIP-0095

NATURAL ELONGATION AND TRIANGULARITY OF LOW ASPECT RATIO TOKAMAK PLASMA/LI Fangzhu ZHANG Jinhua GAO Qingdi et al. (Southwestern Institute of Physics, Chengdu) The dependence of the natural elongation k and triangularity S for low aspect ratio tokamak plasma on the aspect ratio A for different internal inductance l\ and 8 poloidal beta /?p was investigated numerically. It is found that the effects of l\ and /?p on k can be described in terms of an "effective" aspect ratio. Numerical results show that the dependence of k on /; can be explicitly fitted by an expression k= \-\- 2 gi (/;) A~ +g2 (10 A~* and the effect of /5P on k is not negligible. No explicit depen- dence of S on I, and /Jp has been found from these results.

CNIC-01130 960012 ASIPP-0048

ELECTRIC CONDUCnVITY AND BOOTSTRAP CURRENT IN TOKAMAK/ MAO Jianshan WANG Maoquan (Institute of Plasma Physics, Academia Sinica, Hefei) A modified Ohm's law for the electric conductivity calculation is presented, where the modified ohmic current can be compensated by the bootstrap current. A comparison of TEXT tokamak experiment with the theories shows that the modi- fied Ohm's law is a more close approximation to the tokamak experiments than the classical and neoclassical theories and can not lead to the absurb result of Zeu

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NEUTRON AND NUCLEAR PHYSICS

A34.00 Nuclear Properties and Reactions

CNIC-01030 960013 LMPI-0045

Ca ("Si, 3n) &&+/^ftj-'MI:^ T,= -3/2, A

9. 6±S:J ms, EffiS ft65 «^fJ" -33. 26±O. 25 MeVo HALF-LIFE DETERMINATION OF 65Se/XU Xiaoji HUANG Wenxue MA Ruichang et al. (Institute of Modern Physics, Academia, Sinica, Lanzhou) 65Se, a nuclide with T,= -3/2, A = An+l produced in 40Ca (28Si, 3n) reac- tion was identified via its (3-delayed proton emission. A single proton group at 3. 70 + 0. 08 MeV was observed and its half-life was experimentally determined to be 9. 6±4.1 ms which was corresponding to superallowed (3 transition from ground state of 65Se to the isospin analog state, the lowest 7"= 3/2 state, in 65As and the subse- quent proton emission to the ground state of 64Ge. Based on these results combining with coulomb displacement energy calculation, the mass excess of 65Se was obtained as —33- 26±0. 25 MeV.

CNIC-01075 960014 CNDC-0018 INDC (CPR) -040/L &l8:ig&JIiiift COMMUNICATION OF NUCLEAR DATA PROGRESS No. 15 (1996) /YE Bangjiao LIU Tingjin ZHUANG Youxiang et al. (China Nuclear Data Center) This is the 15th issue of Communication of Nuclear Data Progress (CNDP), in which the nuclear data achievements and progress in China during the last year are presented , including measurements of the energy spectrum and angular distributions of protons from stainless steel bombarded by 14-6 MeV neutrons, and of NatNi (n, xa) reaction cross sections; calculating methods is program CCRMN, theoretical calculations of 59Co and 90Zr neutron reaction data, progress in calculation of direct inelastic scattering cross section of neutron, consistent dynamical and statistical de- scription , a set of optical potential parameters of natural zinc; the method and pro- gram CABEI for adjusting consistency between natural and its isotope data,produc- tion cross sections of 18F, 77Br and 186Re medical radioisotopes, evaluations of H total cross section from 20 MeV to 2 GeV, 58.6o.6i.62.64.N«Ni (n> p)? 59CO) 9oZr (n? x) and 84Rb decay data,the comparison of gamma-ray spectrum calculation with se- mi-empirical method and some model codes, nuclear data sheets update for A— 197 and nuclear high-spin data for ^4=174, 176 and 178; thermal reactor benchmark testing of CENDL-2 and ENDF/B-6; the status of CENDL-2- 1 and progress on Chinese Evaluated Nuclear Parameter Library; activities and cooperations on nucle- ar data in China in 1995.

CNIC-01080 960015 SUINST-0012 10 6L>

CROSS SECTIONS OF SMALL ANGLE FAST NEUTRON ELASTIC SCATTER- ING ON 7Li AND 6Li NUCLEI /WAN Dairong DAI Yunsheng ZHANG Kun et al. (Institute of Nuclear Science and Technology, Sichuan University,

Chengdu) (In Chinese} b The elastic scattering cross sections of fast neutrons on 7Li and 6Li nuclei at in- cident angles below 5° are measured by the associated particle time-of-fight method. The corrections for neutron fluence rate attenuation multiple scattering and finite angle geometry are perfomed by using Monte Carlo method. The experimen- tal results are compared with the theoretical calculations based on the optical mod- el. The results may provide data needed in nuclear engineering design.

CNIC-01083 960016 ; ; CNDC-0019 +ttjR^imi+ faitt y-*«^ii6»>Ji:«wit»/*^« m m

, 1000, 1500, Pb, »«Th, 2^

CALCULATIONS OF NUCLEON EMISSION AND ENERGY DEPOSITION OF SPALLATION NEUTRON SOURCES INDUCED BY INTERMEDIATE ENER- GY PROTONS/SHEN Qingbiao TIAN Ye ZHAO Zhixiang et al. (China Insti- tute of Atomic Energy, Beijing) (In Chinese) Monte-Carlo calculations of nucleon emission and energy deposition of spalla- tion neutron sources induced by intermediate energy protons were made. The cas- cade , evaporation, and fission reaction processes are considered in our calculations. The target materials 186W, 208Pb, 232Th, and 238U and incident proton energies 800, 1000, 1500, and 2000 MeV were chosen which are pencil beam on target axis. The number and spectra of neutrons and protons emitted from different regions of the target surface were calculated. The energy conservation is considered approximate- ly , for which the bind energies are obtained according to the mass changing. The ionization energy induced by protons, nuclear recoil energy in cascade processes, and 11 fission fragment energy in different regions inside the target are recorded. The cal- culated results show that the most of the outgoing neutrons are emitted from the front part of the target. Since the target is longer the most of the outgoing neutrons are emitted from 30~ 150 degrees against the zaxis of the target. The calculated re- sults also show that the most part of the deposited ionization energy, nuclear recoil energy, and fission fragment energy are distributed in the front part especially near the z axis of the target.

BOO. oo

CHEMISTRY, MATERIALS AND EARTH SCIENCES

BIO. 00

CHEMISTRY

Chemical and Isotopic Analysis

CNIC-01028 960017

a

M>JO. 050%~1.00%, R»\feWnm$t% 0- 006%~0. THE RESEARCH OF A METHOD FOR DETERMINATION OF TOTAL CAR- BON , COMBINATION CARBON AND FREE CARBON IN BERYLLIUM MET AL/YANG Xingzhong ZHU Xiaohong (Sichuan Institute of Material and Tech- nology, Chengdu) {In Chinese) A method for determination total carbon, combination carbon and free carbon in beryllium metal with LECO CS-344 carbon/sulphur determinator has been stud- 12 ied. Tungsten-copper mixed pellets are used as flux to the determination total car- bon. Ratio of weight of the flux to the sample is greater than 20 • 1. Good analyti- cal results are got. By this method the relative standard deviation is

CNIC-01032 960018 SINRE-0057 TBP feJg

, ICP-

g0^, Al, Ag, Ba, Ca, Cd, Co, Cr, Cu, Fe, In, Li, Mg, Mn, Mo, Ni, Pb, Sn, Ti, V, Y %\ Zn #J$j £ feMfe 0. 2 ~100ng«g-1, @i|Jt**94%~110^, RSD («=8) 2? 0. 8%~6. 2% .

DETERMINATION OF 21 TRACE IMPURITIES IN UO2 WITH TRIBUTYL PHOSPHATE CHROMATOGRAPHIC SEPARATION-USN-INDUCTIVELY COUPLED/ATOMIC EMISSION SPECTROMETRIC /HOU Lieqi WANG Shuan LI Jie (Institute of Nuclear Power of China, Chengdu) {In Chinese) A method of tributyl phosphate chromatographic separation-USN-inductively coupled/atomic emission spectrometric was selected. And the parameters, interfer- ence of acid concentrations, interference of coexisting elements, selecting of flow for carrier gas, solution temperatura were studied. When the sampling amount is 250 mg, the determination range for Al, Ag, Ba, Ca, Cd, Co, Cr, Cu, Fe, In, Li, Mg, Mn, Mo, Ni, Pb, Sn, Ti, V, Y and Zn are 0. 2~100 ng • g"1, recovery are 94%~110%. The RSD ( n =8) are 0. 8%~6. 2%.

CNIC-01061 960019 BNIF-0009

13 Nal, NalO ffl NaIO3. &*W NalO ft NaIO3 ffl#£-JW&JSC>&Nal o J WCO2, fr&M (N2H< • H2O) <£#J N2

NaOH i^W Na2CO3, *t?A£$ Nal

MENUFACTURE OF HIGH PURE SODIUM IODIDE BY IODINE AND SODI- UM CARBONATE/LIANG Baosheng YANG Dehua LU Suxiu et al. (Beijing Nuclear Instrument Factory) (In Chinese) Menufacture of high pure sodium iodide by reaction of iodine and sodium car- bonate has been developed in the production of crystal Nal(Tl) for the detection of radioactivity. The reaction becomes easy at normol atmasphere and temperature with adding a small quantity of Nal to pure water containing iodine and sodium car-

bonate. Products in the reaction is Nal, NalO and NaIO3. Among them NalO and

NaIO3 are reduced to Nal by diamine hydrate. N2 in N2H2 • H2O and CO2 in

Na2CO3 are discharged at the synthetic reaction. The purification process for syn-

thesized Nal is simplified while the use of higher purity of Na2CO3 than NaOH re- sults in the decrease of impurity in Nal. The purity of the end products is high, the yeild is high too.

CNIC-01069 960020 SMI-0011

mzr-

THE RESEARCH OF LITHIUM ISOTOPE IONIZATION MASSS SPECTROME- TRY USING MATERIALS LOAD TECHNOLOGY/WEI Xingjian ZHAO Zhonggang HUA Yongming et al. (Sichuan Materials and Technology Institute, Chengdu) (In Chinese) A method was studied for determining the ratio of 6Li+, 7Li+ ion currents

emitted from Li3PO4 as a material loaded by thermal surface ionization mass spec- trometry. The effects of analysis conditions, such as the sample acidity, the ionizing filament temperature, the vaporized sample filament temperature, the quantity of sample loaded and the ratio versus time were studied. A high precision lithium iso- 14 tope analysis procedure was established. Using the procedure, the related standard deviation of lithium isotope ratio is better than 0. 1 %, and the best is up to 0. 047%. The procedure has the advantages of simplicity of sample making, short time of analysis, no significant effects on the mass fractionation.

CNIC-01071 960021 SINRE-0064 ICP-AES

(ICP-AES) fttftaj^f&flHHfetMn, Mo, Ba, Mg, Cu, Co, Ca, V, Al, Ti, Pb,

10 mg • ml-'ltt, g&$ITW£ 1. 3-33 fig • g-l£|BJ. 0l&« 92%~

DIRECT DETERMINATION OF IMPURITIES IN ZIRCALOY BY ICP-AES/ TANG Bangfu FEI Hao WANG Shu'an (Nuclear Power Institute of China, Chengdu) (In Chinese) Samples of Zircaloy were dissolved in HCl with dropwise addition of HF. The cooled solution was diluted with H2O, and Mn, Mo, Ba, Mg, Cu, Co, Ca, V, Al, Ti, Pb, Ni and Hf were determined directly by inductively coupled plasma atom- ic emission spectrometer (ICP-AES) with matrix-minor components matching. In- terference of coexisted elements and effect of matrix and acidity in the sample solu- tion were discussed. For the sample solution containing 10 mg • ml"' of Zircaloy, the detection limits ranged from 1. 3 to 33 /xg • g -1 of Co and Pb respectively. The rate of recovery is ranging from 92% to 124% , the relative standard deviation is within 7%.

CNIC-01077 960022 IAE-0155 M m c CPWR>

PWR zmw7tft*®Mmmw&. &#*3 K, ^mmm^Mo, TC, RU, Rh, pa, Zr, Fe, Cr, Ni -^7t^6

DEIERMINATION OF CHEMICAL COMPOSITION OF INSOLUBLE RESIDUE OF SPENT FUEL BY TOTAL REFLECTION X-RAY FLUORES- CENCE SPECTROMETRY/JIN Liyun HUANG Qingliang YUAN Hui et al. 15 (China Institute of Atomic Energy, Beijing) (In Chinese) The analysis method of chemical composition of insoluble residue of spent PWR fuel has been developed by using a self-made prototype of total reflection X- ray fluorescence spectrometer. The simulated sample of insoluble residue of spent PWR fuel was analyzed by two sample preparation methods including microwave decomposition-solution prepared sample and particle suspension direct prepared sample. The contents of Mo, Tc, Ru, Rh, Pd, Zr, Fe, Cr, Ni, etc. are determined simultaneously by taking 3 fig of sample. The precision (RSD) of 3%~15% are reached. It is predicated that the method could also be applied to practical sample analysis of insoluble residue of spent PWR fuel.

CNIC-01097 960023 IAE-0158

'\

DETERMINATION OF MIXTURE VALENCE PLUTONIUM AND MULTI- COMPONENT BY COMPUTER RESOLUTION ANALYSIS OF ABSORPTION SPECTRUM (UV/VIS/NIR) (CRAAS) /ZHUANG Weixin YE Guoan HUANG Lifeng et al. (China Institute of Atomic Energy, Beijing) A spectrophotometry has been developed which can directly determine a multi- component sample by spectrophotometry without any chemical separation. CRAAS (Computer Resolution Analysis of Absorption Spectrum) has been created. It is dif- ferent from the previous spectrophotometry depending on only one or several special absorption peak. The CRAAS deals with the whole region of absorption spectrum by mathematical statistics. So CRAAS has higher accuracy, stronger power and very high resolution. The trouble comes from overlap of different spectrum in each other has been solved because CRAAS depends on the whole spectrum. As long as two spectra have different shape, their concentrations can be determinated even their special absorption peaks are, seriously overlapped. The accuracy is about

±R0/

16 CNIC-01098 0024 iAE-0159 m/Hit #

(CRAIS) w mirVft'r' 2; (CR/•\AS) CRAIS BP. tr 5- W

DETERMINATION OF URANIUM AND/OR ACID CONCENTRATION BY COMPUTER RESOLUTION ANALYSIS OF INFORMATION SPECTRUM (CRAIS) /ZHUANG Weixin HUANG Lifeng SUN Hongfang (China Institute of Atomic Energy, Beijing) CRAIS (Computer Resolution Analysis of Information Spectrum) is a devel- opment work of CRAAS ( Computer Resolution Analysis of Absorption Spectrum). CRAIS is a direct spectrophotmetry method which is applied to deter- mination of concentration of uranium and nitric acid. That is one absorption spec- + trum of UO2 -HNO3 decomposed into two information spectra, "Zero acidity urani- um spectrum" and "Acid information spectrum". These two information spectra will be taken as standard spectra and saved in the computer for analysis. To deter- mine the concentration of uranium and acidity in UO^-HNO,, solution , by scanning to obtain a spectrum of sample with spectrophotometer and running CRAIS pro- gram based on the spectrum and two information spectra, the concentration of ura- nium and nitric acid will be calculated out directly. The accuracy is about +5%-

CNIC-01115 960025 SINRE-0070

Cr Cu Fe Li Mn Al, Ca- ' > > ' ' - < Mo, Ni, Pb, Sn, V, 0. 01 ,xg. g-'~0. 04 4. 2%~107. 3%, RSD (n=8) % 0. 82%~6- 4%. ^

THE STUDY DETERMINATION OF 18 TRACE IMPURITY ELEMENTS IN NUCLEAR-PURITY GRAPHITE BY USN-ICP/AES/HOU Lieqi WANG Shu'an LI Jie (Nuclear Power Institute of China, Chengdu) (In Chinese) 17 Using ultrasonic atomization-inductively coupled/atomic emission spectrome- try, the determination of 18 impurity elements in nuclear-purity graphite has been studied experimentally. They are Al, Ca, Cd, Co, Cr, Cu, Fe, In, Li, Mg, Mn, Mo, Ni, Pb, Sn, V, Y, and Zn. The measuring limits are from 0. 01 to 1 0. 04 fig • g" o The recovery rates are between 94. 2% to 107. 3%. The RSD (n = 8) are from 0. 80% to 6. 4%.

CNIC-01125 960026

STUDY OF CORRECTING THE EFFECT OF DAUGHTER AGE ON DETER- MINING 235U ENRICHMENT OF FUEL RODS/DENG Jingshan ZHOU Cheng- fang LUO Minxuan (The Fifth Research and Design Institute, CNNC, Zhengzhou) LIU Yun (Peking University, Beijing) (In Chinese) Gamma-ray passive technique is a very effective method to assay and deter- mine 23'U enrichment of nuclear power plant fuel rods. There is a weakness in this passive method, i. e. only after the uranium isotope daughters of UO2 pellets have reached to equilibrium with uranium parent, then the 23:>U enrichment can be deter- mined. This weakness greatly restricts the application of the method. A new two- peak and two-window technique is developed that can overcome the interference of uranium daughter decay in determining 235U enrichment of nuclear fuel rods, and the results are very satisfactory. The new technique will play an important role in the gamma-ray passive technique for determining 235U enrichment of fuel rods. This new technique also makes the gamma-ray passive method perfectly.

CNIC-01126 960027 FRDINI-0012

18 COMPUTER APPLICATION IN A NONDESTRUCTIVE TESTING DEVICE FOR DETERMINING 23SU ENRICHMENT/LIU Yun (Beijing Institute of Mod- ern Physics, Peking University, Beijing) DENG Jingshan (Fifth Research and Design Institute, CNNC, Zhengzhou) {In Chinese) The hardware multichannel is replaced by a computer multichannel analyzer in the second generation of nondestructive testing device for determining 235U enrich- ment of fuel element in nuclear power plant. The spectrometric analyzer system consists of the spectrometric analysis board and the multichannel emulator software (PHA). The multichannel scaling system is composed of eight-channel multichan- nel scaling board and the multichannel scaling software (MCS). The digital discrim- ination, self-tracing and self-adjusting of threshold energy, and two-peak and two- window techniques are used to increase the measuring accuracy and testing speed. The automatic loading and unloading and classification of fuel rods are realized by using computer, therefore, the level of automation is upgraded. The method of on- line inspection of rods enrichment with passive gamma-ray can play its role fully due to the application of computer in the second generation of nondestructive test- ing device.

B12-00 Inorganic, Organic and Physical Chemistry

CNIC-01024 960028 SMC-0123 9!fl&fiffi-!?B$*l'fi<)1HRjlW?/& & (^JHIE^) L.N.Edmunds

^^m^fo W^TO. «12 12\timm&%Wm&fttM

forskolin, 8-Br-cGMP # LY-83583 cAMP MmiM.in^^ AC-cAMP-PDE ^SEWg^Hl^fn cGMP

DISSECTION OF THE COUPLINGS BETWEEN CELLULAR MESSENGERS AND THE ORCADIAN CLOCK/TONG Jian (Suzhou Medical College) Leland 19 N. Edmunds (State University of NEW YORK U. S. A) It has been known in recent years that living cells can exhibit circadian rhythms in totally different physiological processes. Intracellular messengers were demonstrated to mediate the entrained pathways linking rhythmic components be- tween circadian clock and its output signallings. Levels of cyclic AMP and cyclic GMP in synchronized cells, and activities of the two key enzymes (AC and PDE) responsible for the cyclic AMP metabolism were measured by applying the isotopic techniques. Bimodal circadian ocillations of the messenger levels and the enzyme ac- tivities were disclosed in LD: 12, 12 cycle and constant darkness, as well as in the dividing and nondividing cultures of the Euglena ZC mutant. Interference experi- ments with the enzyme activator and inhibitor such as forskolin, 8-Br-cGMP and LY 83583, and analysis of the cell division cycle (CDC) and coupling messengers suggested that the peak pulse of cyclic AMP,circadian oscillation of the AC-cAMP- PDE system and phase-dependent regulation by cyclic GMP might be important coupling factors in downstream mediation between the circadian clock and the CDC.

B13.00 Radiochemistry and Nuclear Chemistry

CNIC-01084 960029 HYIT-0003

THEORY STRUCTURE ON DECONTAMINATION TECHNOLOGY FOR PRI- MARY COOLANT LOOP OF IN-SERVICE PRESSURIZED WATER REAC TORS/ZHOU Xianyu (Central-South Institute of Technology, Hengyang, Hunan) (In Chinese) Theory structure on Decontamination Technology for Primary Coolant Loop of In-Service Pressurized Water Reactors is proposed. The paper aims at syste- matizing the experiences accumulated abroad in the development of decontamina- tion over a long period of time and raising them to the level of instructive theory, so as to help form Decontamination Technology for Primary Coolant Loop of In-Ser- 20 vice Pressurized Water Reactors, turn "skill" into "science", and stop acting blindly in the development of decontamination.

CNIC-01086 960030 SUINST-0013

MeVfP 140-160 m HDEHP

In-DTPA $ftMt £mIn-DTPA M IIn-DTPA -^

ftj ft{*##] # 0. 96 0. 00o & DTPA % DTPA ^"'In-DTPA '"In-DTPA ? HPGe 7 it lll t 1 ; # mCi (37 MBq) In-DTPA|ii:M-|4l5tl T -|a-^ t DTPA ^ 20-40 Mgo STUDY ON PREPARATION AND QUALITY CONTROL OF "" In-DTPA RA DIOPHARMACEUTICAL/ZHOU Dehai (Institute of Nuclear Science and Tech- nology, Sichuan University Union , Chengdu) (In Chinese) An electroplated silver target is bambarded by a-particles in the internal target installation of a 120 cm cyclotron. The energy and the beam intensity of the a-par- ticles are 24~25 MeV and 140—'160 f±A respectively. The radiochemical separa- tion of luIn from the irradiated target is carried out by HDEHP solvent extraction. U1 An '" InCl3 injection is prepared from the obtained In and determined. The "'In-DTPA for an ideal cisternography is prepared with diethylenetri- ul aminepentaacetic acid (DTPA) and InCl3 injection. The radiochemical purity of the resulting H1 In-DTPA radiopharmaceutical is checked by paper chromatography or thin layer chromatography (TLC) on silica gel. The Ri values of "'In-DTPA and unreacted ulInCl3 in the radiopharmaceutical are 0. 96 and 0. 00 respectively. The separation and determination of free DTPA and n'In-DTPA in the radiophar- maceutical are realized through the difference of the retention time. The radioactiv- ity of the "'In-DTPA radiopharmaceutical is determined by HPGe Y-ray spectro- metric system. The content of DTPA in the final product is 20~40 fig per mCi (37 MBq) of '"In-DTPA radiopharmaceutical.

21 B20. 00

MATERIALS

B22.00 Metals and Alloys

CNIC-01037 960031 RIPCE-0003

CXPSK m CAES) m- ^ (SIMS> *t , H2, co, co2, H2O

STUDY ON THE SURFACE OXIDATION OF URANIUM IN DIFFERENT GASEOUS ATMOSPHERES/WANG Xiaolin FU Yibei XIE Renshou (South- west Institute of Nuclear Physics and Chemistry, Chengdu) (In Chinese) The studing for the surface oxidation of uranium and oxide by X-ray photo- electron spectroscopy (XPS), Auger electron spectroscopy (AES), secondary ion mass spectroscopy (SIMS)> and the surface oxidation of uranium in different gaseous atmospheres such as O2, H2» CO, CO2, H2O (v) and air were reviewed. The surface oxidation of uranium is greatly influenced by a number of parameters including atmospheric temperature, pressure, diffusion of adsorded gas atoms through the oxide layer, surface and interface chemical component, and defect struc- ture and electron nature of the oxide layer. The initial oxidation mechanism and ki- netics have been discussed. Suggestions for future work have also been presented.

CNIC-01042 960032 SINRE-0061

0* Inconel 690, II "• Inconel 690 > Inconel 600 ftJ Incoloy 800 22 Inconel 690

A STUDY OF THE RELEASE RATE OF CORROSION PRODUCTS FOR NU- CLEAR SG TUBING/WEN Yan SU Xingwan (Nuclear Power Institute of Chi- na , Chengdu) (In Chinese) Out-of-core radiation fields mainly are caused by activated corrosion product released from nuclear heat Supply Syslem. It is very important to minimize the gen- eration of radioactive corrosion products which become a radiation Source, in order to meet the needs of operation and maintenance. A study was conducted on deter- minating the general corrosion rate and metal release rate for inconel 690 (Japen), Inconel 690 (China) , Inconel 600 and Incoloy 800 tubes on the primary water side of nuclear power plant simulation. The results show that the release rates of corro- sion products of Alloy 690 on the primary water side is very low and that they de- crease with the increase of chromium content in the alloys.

CNIC-01066 960033 LENP-0005 Mo + C, Ti + C

c m Mo f1) Ti )l;A H13 10. 8 125

> MoC fll Fe2MoC n. & 700

H13 533 ^o T.+C iv. Hi 3 Tie

l/640o min C A STUDY OF THE MECHANISM OF CORROSION RESISTANCE FOR Mo + C and Ti+C DUAL IMPLANTED H13 STEEL/ZHANG Tonghe WANG Xiaoyan (Institute of Low Energy Nuclear Physics, Beijing Normal University, Beijing) ZHAO Weijiang XUE Jianming (Institute of Heavy Ion, Peking University, Bei- jing) (In Chinese) The behaviors of corrosion resistance of Mo, Ti as well as the Mo+C and Ti 23 +C implanted Hi 3 steel were studied and compared. The results showed that the corrosion currents of Mo ion and Ti ion implanted H13 steels were 10. 8 and 125 times smaller than the HI 3 steel respectively. It was found from TEM and SEM observations that smaller dispersive phases of Ti-or Mo-compounds combined into large complexes which inhibited the corrosion. The dispersive phases of the FeMo,

MoC and Fe2MoC were formed and scattered in the grain boundary in Hi 3 steel by Mo+C dual implanting. The grain boundary net was filled by MoC phases. It was found from SEM observation that after 700 minutes of corrosion, the successive an- ti-corrosion layers was formed from dense MoC grain boundary nets. The corrosion current for the Mo + C implanted steel is 533 times smaller than Hi3 steel. The continuous layers of Ti-iron and TiC phases were formed in HI3 steel by Ti+C du- al ion implant. It made substantial improvement on the corrosion resistance perfor- mance. The corrosion current was reduced by a factor of 640. It was observed from the SEM observation that after 500 minutes of corrosion, no surface morphology changes were observed. This showed that the implanted layer has similar character- istic to ceramic layer which is the best material for corrosion resistance.

CNIC-01073 960034 SINRE-0065

Cr tbiift 2. 1-2. 5 Z.m. u$#:li?& 600-800'CTiD^ 3 h, &&*£&*&£.&%., HJlr

Fe/Cr ttft3S$fi$Ml-9i fB& 700-800'CTinaWp. W^-t^/^ig^JZr (Fe, Cr)2 %

--ffi*fJU. £^rH&M«£-4ffi«t'&.i:fflJ!*;fr*gftMZr (Fe, Cr)2, fi§r& 700~800'C hm 3 h, illf**£te*££3Efl:. Fe/Cr tfcft&i. 9 P$5 i. 5 lEt = ffi*#) Fe ft Cr ^ISfr^K Fe ft Cr ^ffiSrmfi^. «^iA P

H'f.Fe Jj^^WrtkttCr Jjf(^'|*;Cr Mi^/^ fH®Zr (Fe, Cr

Zr (Fe, Cr)2^W:*:. i^aSiKHJtlfiT^-ffiJK^IBI^tt THE EFFECT OF HEAT TREATMENTS ON THE STRUCTURE AND COMPO- SITION OF SECOND PHASE PARTICLES IN ZIRCALOY-4/ZHOU Bangxin YANG Xiaolin (National Key Lab. for Nuclear Fuel and Materials, Nuclear Power Institute of China, Chengdu) The effect of heat treatments on the structure and composition of second phase 24 particles (SPPs) in Zircaloy-4 was investigated after SPPs separated from alpha zir- conium matrix. After specimens air cooling from heating at 1050°C beta phase, the

SPPs precipitated during cooling are Zr (Fe, Cr)2 with cubic structure, Fe/Cr ratio in Zr (Fe,Cr)2 is fluctuated between 2. 1~2. 5. The cubic crystal structure does not change but only the Fe/Cr ratio decreases gradually to 1. 9 when specimens were reheated at 600 ~ 800 "C for 3 h. Small amount of precipitates with hexagonal

Zr (Fe, Cr)2 can be detected when specimens were reheated at 700~800"C for

3 h.SPPs in Zircaloy-4 plates purchased from factory are hexagonal Zr (Fe, Cr)2 with Fe/Cr ratio decreasing from 1. 9 to 1. 5, when specimens were reheated at 700~800 C for 3 h. It shows that the Fe and Cr atoms in SPPs will diffuse and substitute with those in surrounding matrix, when specimens were heated at a cer- tain temperature. The solid solution content of Cr atoms in hexagonal Zr (Fe, Cr)2 is higher than that in cubic Zr (Fe, Cr)2, and the diffusion rate of Fe atoms is faster than that of Cr atoms. This is the reason that the Fe/Cr ratio of Zr (Fe, Cr)2 SPPs varies with the difference of heat treatments.

CNIC-01074 960035

SINRE-0066 n

650 •

THE EFFECT OF HEAT TREATMENTS ON THE CORROSION BEHAVIOR OF ZIRCALOY-4/ZHOU Bangxin ZHAO Wenjin MIAO Zhi et al. (National Key Lab. for Nuclear Fuel and Materials, Nuclear Power Institute of China, Cheng- du) The effect of penultimate annealing temperature and cooling rate on the corro- sion behavior of Zircaloy-4 cladding tube has been investigated. Both nodular corro- sion and uniform corrosion resistance can be improved obviously after changing the heat treatment from the original annealing at 650 "C to quenching from 830 C (up- 25 per temperature of alpha phase region or lower temperature of beta phase region). Although the nodular corrosion resistance can be improved obviously after quench- ing from beta phase, there was a second transition in the variation between weight gain and exposure time, which shows a poor uniform corrosion resistance after a long exposure time during the autoclave tests. The main factor of affecting corro- sion behavior is the solid solution contents of Fe and Cr in alpha zirconium rather than the size of second phase particles. About 200 /xg/g Fe and Cr super saturated solid solution in alpha zirconium could get good uniform and nodular corrosion resis- tance , but much more solid solution contents of Fe and Cr in alpha zirconium could bring about a trend toward poor uniform corrosion resistance for long-term expo- sure time.

CNIC-01102 960036 siNPc-0005 -fttt«tt*Btt*jg;Kftttftttigiti/i£/hi* «*K# mum

, o/u ttmmiT&T 7.

INFLUENCE OF CARBON MONOXIDE TO THE SURFACE LAYER OF URA- NIUM METAL AND ITS OXIDES/WANG Xiaolin FU Yibei XIE Renshou et al. (Southwest Institute of Nuclear Physics and Chemistry, Chengdu) (In Chinese)

The surface structures of uranium metal and triuranium octaoxide (U3O8) and the influence of carbon monoxide to the surface layers have been studied by X-ray photoelectron spectroscopy (XPS). After exposure to carbon monoxide, contents of oxygen in the surface oxides of uranium metal and U3O8 are decreased and O/U ra- tios decrease 1. 2% , 8. 0% respectively. The investigation indicated the surface lay- ers of uranium metal and its oxides were forbidden to further oxidation in the atmo- sphere of carbon monoxide.

CNIC-01108 960037

26 zr-4 ft is/8

TEM STUDY OF MICROSTRUCTURE IN EXPLOSIVE WELDED JOINTS BE- TWEEN ZIRCALOY-4 AND STAINLESS STEEL/ZHOU Hairong ZHOU Bangxin (Nuclear Fuel and Materials Lab. , Nuclear Power Institute of China, Chengdu) The microstructure of explosive welded joints between Zircaloy-4 and 18/8 stainless steel has been investigated by transmission electron microscopy (TEM). The metallurgical bonding was achieved by combining effect of diffusion and local melting when the explosive parameters were selected correctly. The molten region which consists of amorphous and crystalline with hexagonal crystal structure is hard and brittle. But the welded joints can be pullled, bent and cold rolled without cracks formed on the bonding layer, so as the molten regions are small and dis- tributed as isolated islands.

CNIC-01111 960038 SlNRE-0069

Fe/Cr \tm% 1. 75 ft 4. 50 M Zr(Fe,Cr)2 &JS |BJ4fc£-«| .

ZrO2, Rift & a-Fe(Cr) ,«m^^t4^,3l^r ZrO2 O4<> Fe ft Cr ^IS^Hf.Fe HH^rtfrMtt Cr zr-4 £&j*rf4ti:tlft

CORROSION BEHAVIOR OF Zr(Fe,Cr)2 METALLIC COMPOUNDS IN SU- PERHEATED STEAM/ZHOU Bangxin LI Cong MIAO Zhi (Nuclear Fuel and Materials Lab. , Nuclear Power Institute of China, Chengdu) DAI Jiyan (Labora- tory of Atomic Imaging of solids, Institute of Metal Research Academia Sinica, )

Zr(Fe,Cr)2 metallic compounds with different Fe/Cr ratio of 1. 75 and 4. 50 27 were prepared by non-consumable arc melting. X-ray diffraction, electron micro- probe and transmission electron microscopy (TEM) were employed for analyzing the structure, morphology and re-distribution of composition after the autoclave test of Zr(Fe,Cr)2 powder at 500 *C superheated steam with different exposure time. The corrosion products are the same for Zr(Fe,Cr)2 with different Fe/Cr ra- tio,but Zr(Fe,Cr)2 with Fe/Cr ratio of 1. 75 is more resistance to corrosion than that with Fe/Cr ratio of 4. 50. Cubic ZrO2 and alpha Fe-Cr are formed at the begin- ning of Zr(Fe,Cr)2 oxidation,then monoclinic ZrO2 transformed from cubic ZrO2 and (Fe,Cr)3O4 are observed late. When the segregation of iron and chromium atoms occurs during the oxidation of Zr(Fe,Cr)2 metallic compound,the diffusion rate of iron atoms is faster than that of chromium atoms. Cubic Zr6(Fe,Cr)3O phase which is coherent with the lattice of Zr(Fe,Cr)2 on the relationship of

(122)zr

CNIC-01123 960039 SINRE-0074

NO A'flW*H, o. 5%Ni-o. sKMo^H^MftLMM; If Ttio.5 *£ * m w, a & -#. *) u w w, m <® m •% x £ , ® m x % ^ ^i IT M , & 1050C/0. 5 h /K^ + 810C71 h fim; i55iiffl^ftffe!Jffe^lli5g, "#Afl £&$.•, 4 %Ni IS 2%Ni -&m®R 0. 5Ni-0. 5%Mo

THE STUDY OF HIGH-BORON STEEL AND HIGH-BORON CAST IRON USED FOR SHIELD /PAN Xuerong LU Jixin WEN Yaozeng et al. (Nuclear Power Institute of China, Chengdu) (In Chinese) The smelting, forging, heat-treatment technology and the mechanical proper- ties of three kinds of high-boron steels (type 1 : 0. 5% boron; type 2: 0. 5% boron and 4 % or 2 % nickel; type 3 : 0. 5% boron, 0. 5% nickel and 0. 5% molybdenum ) were studied. The test results show that the technology for smelting, forging and heat -treatment (1050 C/0. 5 h water cooled + 810'C/l h oil cooled ) in laboratory is feasible . Being sensitive to notch, the impact toughness of high-boron steel type 28 1 is not steady and can not meet the technology requirements on mechanical proper- ties. The mechanical properties of both high-boron steel type 2 and type 3 can meet the technological requirements. The smelting technology of high-boron casting iron cantaining 0. 5% boron was researched. The tests show that this casting iron can be smelted in laboratory and its properties can basically satisfy the technology re- quirements.

B23.00 Ceramics and Cermets

CNIC-01033 960040 SINRE-0058

Gd2o3-uo2 W*fc

E"M 93- 5%~

96. 5%, fii^JfifaM^#W£i5i+MMSM«ffl Gd2O3-UO2 S*.

STUDY ON FACTORS AFFECTING SINTERING DENSITY OF Gd,O3-UO2 PELLETS/ZHU Shuming ZOU Congpei YANG Jing et al. (NUCLEAR POWER INSTITUTE OF CHINA, CHENGDU) Un Chinese)

The sintered density of Gd2O3-UO2 burnable poison fuel pellets is an important quality index and is one of main QC items. Therefore, the efforts were made to in- vestigate the factors affecting the sintered density of Gd2O3-UO2» that is, the influ- ences of pre-treatment of Gd2O3 powder, additives, mixing methods and time, sin- tering atmosphere, sintering temperature and time on the final density of Gd2O3-

UO2 pellets contained 0, 3% , 7% , and 10% (mass percentage) Gd2O3. The results show: the pre-treatment is useful for improving the distribution of Gd2O3; the addi- tive of ammonium oxalate will effectively adjust the density of pellets; 1750'C is the suitable sintering temperature. The proper process parameters have been obtained, and the Gd2O3-UO2 pellets prepared for in-pile irradiation test meet the design re- quirements for the density (93- 5%~96. 5% of T. D. ), homogeneity, microstruc- ture, etc. 29 B24.00 Other Materials

CNIC-01087 960041 ASIPP-0047

m

, nao. i moi/L

DOSE EFFECTS ON DAMAGE OF THYMIDYLIC ACID AND ITS COMPO- NENTS IRRADIATED BY A N+ ION BEAM/SHAO Chunlin YU Zengliang (Institute of Plasma Physics, Academia Sinica, Hefei) Research into damage of DNA components is an important field in mechanism study to the low energy ion beam irradiation. It was found that the UV difference spectra of irradiated thymine (T) had two positive peaks caused by the changes of 7r electron conjugation of the pyrimidine ring, and that the residual activity of T sample irradiated by a N+ ion beam was not influenced by treatments of acid and al- kali as well as heat- In addition, the residual activities of irradiated thymidine (dTR) and thymidine 5'-phosphate (5'-dTMP) with and without treating of strong acid and strong alkali were also measured. With UV absorption spectropho- tometry, the yield of T released from the irradiated samples of dTR and 5'-dTMP and the residual concentration of these target molecules were deduced, and it was found that the yield of T increased when the solution of the irradiated dTR sample was treated by heat but decreased when this solution was treated by acid and alkali for these treatments splitting T* of T*-S or T*-S-P. On the other hand, the yield of inorganic phosphate released from the irradiated 5'-dTMP was investigated and 30 found that it was increased by the treatment of alkali and that the increase degree was depended on the time scale of the treatment. Moreover* G(Pi) of the irradiated 5'-dTMP non-linearly decreased with increasing dose.

B30. 00

EARTH SCIENCES

B31 00 Land

CNIC-01027 960042 BRIUG-0027

THE CHARACTERISTICS OF SODA METASOMATITE TYPE URANIUM MINERALIZATION FOR PROTEROZOIC STRATA IN THE CENTRAL- SOUTHERN PART OF KANG-DIAN EARTHS AXIS/QIAN Farong (Beijing re search Institute of Uranium Geology) (In Chinese) The uranium mineralization for Proterozoic strata in the central-southern part of Kang-Dian earth's axis can be divided into four typies (sandstone, soda metaso- matite, proterozoic epimetamorphics and quartzite). The soda metasomatite type is the dominant type of uranium mineralization and has the prospecting potential in the area. The characteristics of this type uranium mineralization and the problems of metallogensis are discussed. Soda metasomatite type uranium mineralization is controlled by sode metasomatite and structure. Uranium exists mainly in che forms of minerals (pitchblende, uranite). Its cell parameter is high and oxygenated coffi- cieut is low, belonging to moderate-low temperature hydrothermal origin. The met- 31 allogenetic matarials originated from deep-seated crust and country rocks. The met- allogenetic solution includes a great quantity of atmospheric water, besides hy- drothermal solution from deep-seated crust. The metallogene under went the two stages i. e. Jinnin and Chengjiang.

CNIC-01044 960043 BRIUG-0028

METALLOGENIC CHARACTERISTICS OF VOLCANIC HYDROTHERMAL TYPE U-Au-POLYMETALLIC DEPOSITS IN YANSHAN- RE GION/LUO Yi ZHOU Dean HE Yiqiang et al. (Beijing Research Institute of Uranium Geology) Yanshan-Liaoning area is located in the east part of the northern margin of North-China platform. It is a famous metallogenic region of Mesozoic volcanic hy- drothermal type U-Au-polymetallic deposits in the country. The metallogenesis is controlled by a united Late Mesozoic continental taphrogenic volcano-magmatic ac- tivity. The metallogenic epoches are concentrated in Late Jurassic-Early Cretaceous periods. The metallogenic media are moderate and moderate-low temperature vol- canic hydrothermal solutions originated from the mixing of volcano-magmatic wa- ter , metamorphic water and atomspheric water. The ore-forming materials are mainly derived from enrichment type upper mantle and lower crust.

CNIC-01045 960044 BRIUG-0029

, -£fl1JiNBSSRM962a,UB1fqUB2

32 HNO3+HF J

AN IMPROVED TECHNIQUE FOR FISSION TRACK DATING/ZHAO Yunlong ZHAI Pengji WU Zhaohui et al. (Beijing Research Institute of Uranium Geol- ogy) (In Chinese) The necessity of improving the fission track dating (FTD) technique both at home and abroad is illustrated. The ways of making such improvement are also proposed. It is suggested to calibrate the constant b value of the uranium standard glass by using the method of fission products activity. The 3 kinds of uranium standard glass which have been calibrated are NBS SRM962a, UB] and UB2. A es- tablished new method a •

CNIC-01047 960045 BRIUG-0030

33 THE SILICEOUS-CALCAREOUS-ARGILLACEOUS ROCK TYPE URANIUM DEPOSIT IN SOUTH SUBZONE OF WESTERN QINLING/QIAN Farong ZHOU Dean JI Hongfang Beijing Research Institute of Uranium Geology) (In Chinese) The siliceous-calcareous-argillaceous rock type uranium deposit in south sub- zone of western Qinling is an inland found type deposit with specific mineralization and good potentiality. The mineralization distributes along definite horizons and oc- curs in siliceous layer and lenses of siliceous-calcareous rocks. Orebody presents in forms of stratoid, lenticular and irregular veins and controlled by fractural struc- tures. Ore is identified as massive and sandy and each characterized by various min- eral compositions and element associations. The study shows that the mineralizing materials are mainly derived from ore-bearing strata; The metallogenic environment has characteristics of middle-low temperature and supergene; The metallogenesis underwent three stages: (1) Sedimentation-diagenesis of the ore-bearing strata led to preliminery concentration of uranium; (2) Polytectonic activities accompanied by underground hydrothermal process resulted in the industral concentration of urani- um; and (3) Orebody reworked by oxidation-denudation and leaching, locally has taken place secondary concentration. The deposit in origin attributes to polygenesis dominated by underground hydrothermal metallogenesis. Main metallogenic epoch happens during the periods of Late Yanshan and Himalayan. According to the geo- logical-tectonic conditions the further prospecting direction in study area is pro- posed.

CNIC-01055 960046 CIRP-0013

(ARCL) Wttg^rfto X*¥frmT ARCL

34 STUDY ON ARCL ESTIMATION METHOD FOR RADIOACTIVITY-CONTAM- INATED SOIL/LIU Keqiang WANG Zhiming JI Guoqing (China Institute for Radiation Protection, Taiyuan Shanxi) The aim of present work is to discuss the estimation method of allowable resid- ual contamination levels (ARCL) in radioactivity-contaminated soil near by the nu- clear facilities under decommissioning or to be decommissioned. The estimation method would help recommend the regulatory limit on remedial actions for a given site. The methodology of estimating ARCL, the related models and the parameters used for estimation of maximum annual dose are described. As a estimation exam- ple, a contaminated factory site is considered. The maximum individual doses and ARCL values resulting from various radionuclides are estimated. It must be pointed out that the determination of ARCL is also based on the acceptable dose limit. Thus the cost-effectiveness analysis is necessary in determining the actual accept- able dose limit.

CNIC-01067 960047 GiEC-oooi IW3£«l2£^££fftfcmft5 (^&M^> M)

AN ANALYTIC METHOD FOR DETERMINING ASTRONOMICAL IMUTHS/JIA Jingyun (Geological Institute of East China, Jiangxi) {In Chinese) The analytic method for determining astronomical azimuths is a new means, put forward recently by the writer, and a new theory as well. Its essence is as fol- lows. Suppose that near the diurnal apparent motion circle of the Polaris exist a fit- ting ellipse, with the north celestial pole as its centre, the observer's meridian as its 35 ordinate axis, a and b as its major radius and minor radius separately. Measure the zenith distances ( z-, ) and the horizontal directions ( y, ) of the Polaris continually, the horizontal direction of a target on the earth used as the starting horizontal direc- tion. Then transform the two groups of measurements ( Z;,j>i ) into the values ( x,, y, ) which are regarded as the observed values to the ellipse. Initialize the centre of the ellipse ( xo,yo ). Then form the conditional equations of the ellipse and solve the conditional equations by the method of least squares. After several iterations the astronomical azimuth of the target on the earth is obtained (an==360° — y0). Theo- retically the astronomical measurement bears no relation to the time by this method. The operation can be executed easily. This is an ideal and effectual method for directing isolated horizontal control networks in the geological surveying.

CNIC-01085 960048 BRIUG-0030

jij r- INVESTIGATION AND APPLICATION OF MERCURY-THERMAL-SPEC- TRUM-SURVEYS METHOD FOR URANIUM PROSPECTING/YOU Yunfei LU Shili ZHU Jiechen et al. (Beijing Research Institute of Uranium Geology, CNNC) ZHANG Yucang (Geological Party NO. 247, Northeast Bureau of Geo- logic Exploration of Nuclear Industry, Baodi, Tianjin) (.In Chinese) A study on uranium prospecting with Mercury-Thermal-Spectrum-Surveys is presented. The study mainly includes: proving the prospecting mechanism of the method is that the Mercury-Thermal-Spectrum of rock is obviously different from that of uranium ore; applicating microcomputer technology to Mercury-Thermal- Spectrum-Analysis, so as to automate the process and to raise analytical precision. A vertical zoning feature of Mercury-Thermal-Spectrum in uranium deposit NO. 460 has been found and the method has been successfully applied to locate deep ura- nium orebodies at Xidashan section of NO. 460 ore region.

36 CNIC-01089 960049 BRIUG-0031 m:A&ifo*ft®®i&iir&ftti-tftJ5L&ikmMm&w ®m% mm.

a) (2)

ANALYSIS OF URANIUM METALLOGENIC CONDITIONS AND PROSPEC- TIVE PROGNOSIS ON THE SOUTH-CENTRAL PART OF THE XIKANG- YUNNAN AXIS/GUO Baochi QIAN Farong CAI Yuqi ZHANG Daishi (Bei- jing Research Institute of Uranium Geology) (In Chinese) Three types of uranium mineralizations (i. e. , sandstone type, sodium metaso- matite type and Proterozoic epimetamorphic rock type) are distinguished in the south-central part of the Xikang-Yunnan Axis, and their major characteristics are expounded. It is proposed that the Early Proterozoic crust has evoluted three stages; primitive oldland formation stage,subsidence stage and basemental reconsol- idation stage, and that the Middle Proterozoic Kunyang Group is different from typic carbonate-siliceous-pelitic sedimentary formation which contains many region- al uranium-rich horizons. The primitive uranium contents of some-rocks in the re- gion have been studied for the first time, and proposed a new knowledge that some ralative rocks be recongnized as the uranium source rocks of the region. It is pointed out that there are two kinds of hydrothermal alterations, namely, alkaline alteration and acidic alteration, and some areas with development of alkaline alteration have promissing uranium-metallogenic potential. As for the U-metallogenic prospect of

the region, three conclusions are summarized: (1) This region does not have favourable geologic conditions for the Australian-Canadian type Proterozoic uncon- formity-related uranium deposit; (2) The Proterozoic unconformity different from that of Australian-Canadian type does not have promissing U-metallogenic potential either; (3) The alkaline (sodium) metasomatite type uranium mineralization in the 37 region has some prospecting potential. Therefore on the basis of above-mentioned conclusions five relatively promissing uranium-metallogenic prospects are selected.

CNIC-01104 960050 GiEC-0002

STUDIES OF GEOTHERMAL BACKGROUND AND ISOTOPIC GEOCHEM- ISTRY OF THERMAL WATERS IN JIANGXI PROVINCE/ZHOU Wenbin SUN Zhanxue LI Xueli et al. (East China Geological Institute, Linchuan, Jiangxi) The terrestrial heat flow measurement, isotope and geochemical techniques have been systematically applied to the geothermal systems in Jiangxi Province. Re- sults show that the thermal waters in the study area all belong to the low-medium temperature convective geothermal system, which essentially differs from high tem- perature geothermal systems with deep magmatic heat sources. It has been proven that the isotope and geochemical techniques are very useful and effective in geother- mal exploration.

CNIC 01109 960051 BRIUG-0032

^ 125-135 Ma. ^in&Eftr^M^'Hu^M8JK

THE STUDIES OF ISOTOPE GEOLOGY AND URANIUM METALLOGENIC 38 CONDITION OF IGNEOUS ROCKS IN GUYUAN AREA/XIA Yuliang LIN Jinrong ZHU Jiechen et al. (Beijing Research Institute of Uranium Geology) (In Chinese) The results of systematic studies of geochronology, geochemistry and uranium metallogenic condition of volcanic rocks and granites in Guyuan-Duolun Basin are reported. The isotope geological ages of volcanic rocks of Zhangjiakuo Formation and Huajiying Formation are dated between 125 —135 Ma which belongs to early Cretaceous. The investigation demonstrates that granitic magmatic activities in the region had occurred during pre- Variscian, Variscian, Indo-China and Yanshan pori- ods, and that three EW-extending Variscian granitic magmatic activity belts do not exist in the region. The volcanic rocks in the area could be divided into calc-alkali and alkali-calc rocks which were derived from different-degree partial melting of the same or similar component material source, whithout obvious magmatic differ- entiation. There are two types of granitoids: syntectic type and reform type, the former was derived from the lower crust and the later was derived from the upper crust. Reginal uranium mineralizations in the region had multi-stage characteristics. The superimposition of uranium mineralization in the same uranium deposit was the prerequisite of forming the rich uranium body. It is also indicated that the volcanic rocks in this region have low uranium content, which are unfavourable for the forming of uranium deposit. However, even in the relatively unfavourable geological settings there are still some places and rocks which are favourable for uranium min- eralization and the goal of further uranium resource investigation should concentrate on them.

CNIC-01114 960052 BRIUG-0033 «rK

m

39 r, # STUDIES ON HYDROGEOLOGICAL CONDITIONS FOR MINERALIZATION OF SOME SANDSTONE TYPE URANIUM DEPOSIT/WANG Zhiming LI Sen XIAO Feng et al. (Beijing Research Institute of Uranium Geology) (In Chinese) Based on the analysis for regional geology, structural and hydrogeological con- ditions of Erennaoer Depression, Erlian Basin, the hydrogeological hydraulic zoning was carried out for groundwater in the study area,structural-palaeo-hydrogeological stages and the feature of deep-seated groundwater were studied, and, two important U-mineralization periods were determined. The conditions of recharge, runoff and discharge of groundwater in orebearing aquifers and the hydraulic mechanism were revealed by isotope hydrology and single-well tracing technique. By study of hydro- geochemistry , it is indicated that both Subeng and Nuheting U-deposit are located at the parts where groundwater characteristics intensely variated, and the ore indi- caters are determined. Oil and gas transportation and the relationships between groundwater and U-metallogenetic process were discussed by using of organic geo- chemistry method. It shows that the bleeding of oil and gas is very important for the forming of U-deposits. It is suggested that the interlayered oxidation zone type sandstone U-deposit which is suitable for in-situ leaching could be existed in the Tenggeer formation, Bayanhua group of Lower Cretaceous, accordingly, two prospecting areas are delimitated.

CNIC-01128 960053 BRIUG-0034

THE FORMATION MECHANISM AND PROGNOSIS ON THE PROSPECT OF 40 PEGMATITE TYPE URANIUM DEPOSITE IN EASTERN QINLING OF CHI NA/FENG Mingyue RONG Jiashu SUN Zhifu et al. (Beijing Research Institute of Uranium Geology) LIU Qifeng (North-West of Geologic Exploration of Nu- clear Industry, Xi'an) (In Chinese) Lithologies of Qinling Group are composed of pelite-felsic metamorphic rocks, basic metamorphic rocks and calcareous metamorphic rocks. The Pelite-felsic meta- morphic rocks accout for the most part of the sequence and the bulk of the Qinling Group. The Pelite-felsic metamorphic rocks associated with uranium-hosting peg- matite are characterized by high content of SiO2 and alkali, higher content of potas- sium than that of sodium, and moderate content of uranium. The granites in East- ern Qinling can be devided into two genetic types, i. e. I-type and S-type. Three types of pegmatites located in the study region can be attributed to one series of unified evolution of remelting magma and are connected with each other, as well as differ from each other. They resulted from partial melting of Qinling Group. U- hosting pegmatite is the new U-hosting body. The pegmatite-type uranium deposite are of new type too. The formation of such deposit is attributed to gaseous transfer differen-tiation. The plate subduction of recent tectonic regium, the dome-formed granite massif, the pegmatite vein system that resulted from the metamorphism of Qinhng Group occurred in Qinling during Early Paleozoic are the main conditions for the formation of pegmatite-type uranium deposits.

B33- 00 Atmosphere

CNIC-01041 960054 LKNP-0004

ft. ffl&##f PIXE (Particle Induced X-ray

ma

41 INVESTIGATION OF THE PARTICULATE DERIVED FROM INDIGENOUS ZINC SMELTING USING THE NUCLEAR ANALYTICAL TECHNIQUE/ZHU Guanghua (Institute of Low Energy Nuclear Physics, Beijing Normal University, Beijing) (In Chinese) The air particulate samples at the site of indigenous zinc smelting in south of China, using an 8-stage cascade impactor have been collected. The elemental con- centrations of the samples were analyzed by PIXE (Particle Induced X-ray Emis- sion) method. As a result, the mass concentrations of more than 17 elements and their size distribution spectra were obtained. Then the data were analyzed by the absolute principal component analysis (APCA) to evaluate principal components and the percent variance explained by them. From the elemental size distribution spectra, three kinds of patterns were found that they corresponded with the tree principal components and suggested that they were from ore vapor, coal burning and soil dust. Based on the elemental size distribution spectra and a deposit model the deposited amounts for several elements in a human's lung during a day were cal- culated and compared with other places. It is shown that the air quality was heavily degrade at the site of indigenous zinc smelting.

COO. 00

LIFE SCIENCES

cio. oo

ALL EFFECTS AND VARIOUS ASPECTS OF EXTERNAL RADIATION IN BIOLOGY

C13. 00 Effects of External Radiation on Plants

42 CNIC-01100 960055 CSNAS-0109

W. (l) JtJB. (2)

THE MEASUREMENT OF TRANSLOCATION VELOCITY DISTRIBUTION PROFILE OF PHOTOSYNTHATE IN CROP'S TRANSPORTING PATHWAY/ GE Cailin LUO Shishi GONG Jiang et al. (Agricultural College, Uni- versity, ) {In Chinese) The principle and the method for measuring the distribution probability of photosynthate transporting from source to pool in different velocity regions were es- tablished. The method for making the translocation velocity distribution probability pattern of photosynthate was also given. The distribution profile of photosynthate transportation velocity in cucumber and rice have been measured. The results showed : (1) the transportation velocity distribution profile of photosynthate in cu cumber was similar to that in rice; (2) although the translocation velocity of photo- synthate distributed from 0 to the maximum velocity, it was appearent that most of the photosynthate molecules moved at relatively high velocity.

C20.00

RADIOISOTOPE EFFECTS AND KINETICS

C2i.oo Tissue Distribution, Metabolism, Toxicology and Removal of Radioisotopes

CNIC-01021 960056 CSNAS-0096 &ftfc|-ftfflaB#+'0Sr. '"Cs £*flt)¥$Mffi[ *TSr, '"Cs

43 ± 18 ^n 169 EARLY PREDICTION OF 90Sr AND 137Cs CONTENT IN EDIBLE PARTS OF CROPS AND SELECTION OF PLANTS WITH HIGH UPTAKE ABILITY/Zhao Wenhu Xu Shiming Hou Lanxin et al. (Institute of Unclear-Agricultural Sci- ences, CNNC, Beijing) (In Chinese) The uptake characteristics to 90Sr and 137Cs of nine kinds of crops, including spring wheat, rice, soybean, vegetables etc. , were studied from seedling to maturi- ty. The change of 90Sr content per unit of dry weight can be classified into two types the 90Sr content kept in the same level during the whole growing season and kept increasing with the growing period until it came to the maximum point at the time of maturity. 90Sr and 137Cs in the aerial part of plants were mainly dis- tributed in leaves, but the amounts in seeds and fruits were less. The content of 90Sr decreased but the content of 137Cs increased from young to old leaves. So it could be concluded that early prediction of the radioactive content of edible parts according to the content of young leaves was possible. Selection of 169 species in 18 families of plants with high uptake ability of 90Sr and 13?Cs, which grow in Qinshan region near a nuclear power plant and in Beijing region, is also reported.

CNIC-01049 960057 sMc-0125

: SZ39

5. 73-144. 8, & Aft 1*9 3/ 2- 97-3. 25, IS^JJfll^Irtfi<tlH], Tl/2. & 1. 6 h, Tm,% 39 h, m&m Sfe* fl fr

, 45%, 57%fP 33% ( P <0. 01-0. 005) 44 STUDY ON QUALITATIVE IMAGING DIAGNOSIS OF HUMAN BRAIN GLIOMA WITH IMMUNO-RADIONUCLIDE /HUANG Qiang LAN Qing LI Xiaonan et al. (Suzhou Medical College) (In Chinese) The target imaging agent 131I-SZ39 was made by labelling to monoclonal anti- body SZ39 with 131I using modified chloramine T method. On the basis of the biodistribution and pharmacokinetics study in glioma-bearing nude mice and the pa- tients , the qualitative diagnosis of 40 cases with intracranial space-occupying lesion was compared with that of X-CT. The results were satisfactory. SZ39 could deliver 1311 to the target cells specifically. The ratio of target tissues to nontarget tissues was 5. 73~144. 8 in the glioma-bearing animals and 2. 97—3. 25 in the patients at

72 h. The half life of the imaging agent in blood were 1. 6 h ( T1/2a ) and 39 h C 7Y'2P )• The clearing rate was 54% in blood and 80% in urine at 72 h. The sensi- tivity of target qualitative diagnosis was 92%. The accuracy was 82%- The positive prediction rate was 81 % and the negative prediction rate was 91 %. Those of X-CT were 46%, 45%, 57% and 33% respectively ( P < 0. 01 ~ 0. 005 ).

CNIC-01056 960058 CSNAS-0102

® 45 R Zl: 1.85X102Bq, 1.85X103Bq, l.85X104Rq, 1.85X 10-' IV nm, HILI^K rtfffi> JllLJR, ^ 20 *fl| 30?:, %%fcWSr W,Mkm%l%ffl\&ttt] 2. 78%~4. 01%, 3. 04%~4. 4.03%~5.53%. 90Sr^A/S, &&M¥Wmy3 24 h 90.7i%~99.95%tr-If'IR§& #?ft

REGULARITY ON ABSORPTION AND ACCUMULATION OF 90Sr IN YEL- LOW-FEATHER BROILER (HYPECO) /XU Shiming HOU Lanxin ZHAO Wenhu et al. (Institute for Application of Atomic Energy ,CAAS, Beijing) (In Chi- nese) The feeding experiment was carried for yellow-feather broiler (Hypeco) with 90 2 5 Sr [NO3]2 having of 1. 85 X 10 — 1. 85 X 10 Bq/chicken to observe the regular pattern of absorption and accumulation of 90Sr in its organs and tissues. The absorp- 45 tion rate of 90Sr by oral feeding is very low. The most of 90Sr is drained away by daily excreta from the body. The half-time of its feeding is within 24 hours. The more 90Sr is fed, the more 90Sr is absorbed, however, the uptake rate of 90Sr is de- creasing. The affinity of 90Sr for bone is very strony and the partition ratio is about 90% ~99%. The absorption coefficient of 90Sr in organs and tissues of broiler is presented.

CNIC-01063 960059 CSNAS-0104

ANALYSIS OF PHOTOSYNTHATE TRANSLOCATION VELOCITY AND MEA- SUREMENT OF WEIGHTED AVERAGE VELOCITY IN TRANSPORTING PATHWAY OF CROPS/GE Cailin LUO Shishi GONG Jian et al. (Agricultural College, Yangzhou University, Jiansu) The translocation profile pattern of HC-photosynthate along the transporting l4 pathway in crops were monitored by pluse-labelling a mature leaf with CO2. The progressive spreading of translocation profile pattern along the sheath or stem indi- cates that the translocation of photosynthate along the sheath or stem proceed with a range of velocities rather than with just a single velocity. The method for measur- ing the weighted average velocity of photosynthate translocation along the sheath or stem was established in living crops. The weighted average velocity and the maxi- mum velocity of photosynthate translocation along the sheath in rice and maize were measured actually.

CNIC-01070 960060 CSNAS-0106

W90. 6%~99. 3%, 46 o.7%~9.

6.0-0.5.

A DISTRIBUTION OF »°Sr IN CROPS (COTTON, ETC. ) AND SELECTION OF HIGH CONCENTRATION PLANTS FOR 90Sr/HOU Lanxing XU Shiming ZHAO Wenhu et al. (Institute for Application of Atomic Energy, CAAS, Beijing) (In Chinese) Plants absorb 90Sr from soil through the root and transfer 9CSr to above-ground organs. About 90. 6/'o~99. 3% of 90Sr accumulate in stem and leaf,and only about 0. 7% ~9. 4% of its in the kernel. The selection study was made using rice soil around NPP and Beijing drab soil in order to measure the ability of accumulation for 90Sr. The results show that among the test's plants calabash family's plants have the biggest ability and grass family plants have the least one. The absorption coeffi- cient of 90Sr is 16. 8~0. 6 in rice soil and 6. 0~0. 5 in drab soil. It is in good time and economical to select for grass family plants during shooting-booting period, and for calabash family and bean cultures before bud-abloom stage.

C22-00 Radioecology

CNIC-01022 960061 CSNAS-0097

m-r-

ENVIRONMENT ECOLOGICAL EFFECT OF 14 C-CHLORSULFURON AND 47 ITS SAFETY EVALUATION/CHEN Zuyi CHENG Wei (Nanjign Agricultaral University) {In Chinese) The adsorption, migration, degradation, residues of 14C-chlorsulfuron and eco- logical effects of its degradation products were reviewed by isotope trace technique. The results show that: (1) The adsorption of uC-chlorsulfuron in soil are rather weak and its migration are rather strong. (2) The degradation of chlorsulfuron in soils are slow. The bound residues of chlorsulfuron in dryland soil are very consider- able and increasing with the incubation time,extractive residues decrease gradually. By means of TLC and radioactive assay the radioactive degradation products of 14C- chlorsulfuron in soil belong to trinitrogen-aniline. (3) One wheat and rice-wheat seasons after its application, the soil and after-crop (rice) all have considerable residues. The residue of chlorsulfuron and its transfer coefficient are far more than that in its shoots, the latters are more than that in soil. It is not distributed evenly in the plants. The residue in roots is far more than that in plant, which explains clearly that the bad effect of chlorsulfuron on the growth of root is related with its high accumalation on root. (4) The residue products including bound residues of 14C-chlorsulfuron in soils were available on after-crop (maize, bean, pea, rice and garden sass). The damage symptoms showed that the root system development were clearly suppressed and the seedling were effected on growth. The minimun suffer dose of bound residues is 10 /*g/kg in the stage of seedling growth.

CNIC-01025 960062 CSNAS-0098

tr^mm-.

'&M 4 cm £i*]. »'Ce tmm/kffiffl

THE BEHAVIOR OF RADIOACTIVE CERIUM IN AGRICULTURAL ECOSYS- TEM/Zhong Weiliang Wang Shouxiang Chen Chuanqun et al. (Institute of Nu- 48 clear Agricultural Sciences, Zhejiang Agricultural University, Hangzhou) (In Chi- nese) Studies on the transport, accumulation, and distribution of ulCe in simulated paddy and simulated aquatic ecosystem were done. The results are as follows: (1) The concentration of 141Ce in water decreased sharply when 141Ce was put into the paddy through water. The upstake of 141Ce by rice was mainly via root, and redistri- bution in all parts of rice occurred consequently. 141Ce which was rapidly and almost completely adsorbed by soil could not move readily through the soil,and over 93 per cent of that was retained within 4 centimeter of the surface layer. The dynamic be- havior of 141Ce in the paddy could be described as a closed three-compartment mod- el. (2) After 141Ce was put into the aquatic ecosystem, the adsorption, condensa- tion , complexation and deposit of 141 Ce were quickly generated by physical and chemical processes, and then most of that was adsorbed by silt, aquatic plants and animals. Silt had a great capability of adsorbing 141Ce. The concentration capability of aquatic for 141Ce have the order of: hoenwort>snail>fish. A closed five-com- partment model was applied to describe the behavior of )41Ce in the aquatic ecosys- tem.

CNIC-01088 960063 CSNAS-0107 m£±«-fE#>i£&43£lS] **#¥B

(75,150,225 2 > %$k%w-. 75kg/hm m 150 2 g#, m 225 kg/hm

2 , 32. 3%fB22. 4%o tfM&ift£Jff£$!, 225 kg/hm *hS*0ffflEft#J 46% fli

,225

FATE OF NITROGEN IN SOIL-CROP SYSTEM BY NUCLEAR TECHNIQUES EFFECTS OF APPLIED RATE OF AMMONIUM BICARBONATE/CHEN Qing (Department of Plant Nutrition, China Agricultural University, Beijing) WEN 49 Xianfang PAN Jiarong ZHENG Xingyun (Institute for Application of Atomic Energy CAAS, Beijing) The experiment was conducted with 15N tracing techniques in Shijiazhuang from 1994 to 1995. Three nitrogen rates, including optimum rate (150 kg/hm2) based on the recommendation of local farmers, above 50% of optimum rate (225 kg/hm2) and below 50% oi optimum rate (75 kg/hm2) , were selected to study the effect of application rates of ammonium bicarbonate on yield of winter wheat and fate of applied nitrogen under local management and irrigated condition. The results showed that nitrogen uptake and grain yield of wheat under fertilized treatments were higher than those in unfertilized treatment (except 225 kg/hm2 treatment). The highest yield and top dry matler weight (grain 6. 80 t/hm2, top 14. 70 t/hm2) were obtained in optimum N applied treatment (150 kg/hm2),while the highest ni- trogen recovery efficiency (38. 5%) of ammonium bicarbonate by winter wheat was found in below 50% of optimum rate treatment (75 kg/hm2) due to the rela- tively high basic fertility of the field. However, nitrogen recovery efficiency of am- monium bicarbonate decreased with the increasing N application rate. The highest residue of fertilizer N was found in 225 kg/hm2 treatment, and 46% of the residue existed in the top layer of the soil (0~50 cm). The unaccounted N from fertilizer were 30. 20%, 36. 56%, 31-25% in 75 kg/hm2, 150 kg/hm2, 225 kg/hm2 treat- ments respectively according to 15N balance calculation in soil-plant system. The ef- fect of residue N in soil on the next crop, maize, in 225 kg/hm2 treatment was best in three fertilized treatments, suggesting the possibilities of nitrate leaching down in 225 kg/hm2 treatment.

CNIC-01091 960064 cmp-0014

DYFOM-95 &ffim

50 A DYNAMIC FOOD-CHAIN MODEL AND PROGRAM FOR PREDICTING THE RADIOLOGICAL CONSEQUENCES OF NUCLEAR ACCIDENT/HU Er bang GAO Zhanrong ZHANG Heyuan et al. (China Institute for Radiation Pro- tection, Taiyuan) (In Chinese) A dynamic food-chain model and program, DYFOM-95, for predicting the ra- diological consequences of nuclear accident has been developed, which is not only suitable to the West food-chain but also to Chinese food chain. The following pro- cesses, caused by accident release which will make an impact on radionuclide con- centration in the edible parts of vegetable are considered : dry and wet deposition in- terception and initial retention, translocation, percolation, root uptake and tillage. Activity intake rate of animals, effects of processing and activity intake of human through ingestion pathway are also considered in calculations. The effects of leaf area index LAI of vegetable are considered in dry deposition model. A method for calculating the contribution of rain with different period and different intensity to total wet deposition is established. The program contains 1 main code and 5 sub- codes to calculate dry and wet deposition on surface of vegetable and soil. transloca- tion of nuclides in vegetable, nuclide concentration in the edible parts of vegetable and in animal products and activity intake of human and so on.

C40. 00 fr#

APPLIED LIFE SCIENCES

C41.00 gfttttl^Wft Plant Cultivation and Breeding

CNIC-01023 960065 CSNAS-0099

1980-1994

0.&%, nit#itffi*R 374.673 hm2, mt^^A^. 13.793^75,

51 91 m, tt&nm^n^-m r

ADVACES AND PROSPECTS FOR INDUCED MUTATION BREEDING IN HE- LONGJIANG PROVINCE/Sun Guangzu (Heilongjiang Academy of Agricul tural Sciences, Harbin) (In Chinese) Induced mutation breeding employed on soybean, spring wheat, maize, millet, fiber flax,chinese cabbage,kidney been and garlic in Heilongjiang province. Thirty- six new varieties had introduced and released from 1980 to 1994, made up 20. 6% of total released varieties for the same period, accumulated caltivated area of 3. 746 million hm2, and increased the income of formers to $ 168 million; 72 mutants having specific and utilizable values and traits have also been bred in the province. Basal researchs such as radiation breeding in combination with distant hybridiza- tion, biotechnology, and application new induced factors, improving selection meth- ods, have been achieved; 91 articles have been published. These researchs play im- portant role for increasing induced mutation breeding. Three items of suggestion to develop induced mutation breeding are made.

CNIC-01046 960066 CSNAS-0100 *:?-aA*fl«':J-WiS$»&/iE&iI fl 3C \MXJf (fflfSr.'iT*

Wl, t,

5 y it mm. MUTAGENIC EFFECTS OF ION IMPLANTED RICE SEED/WANG Cailian SHEN Mei CHEN Qiufang (Institute for Application of Atomic Energy, Zhejiang Academy of Agricultural Sciences, Hangzhou) (In Chinese) Dry seeds of rice were implanted with 15~30 keV N+ , H+ , Ar+ ion beam of various doses. The biological effects in M^ and mutation in M2 were studied. The results showed that ion beam could induce the variation on the chromosome struc- 52 ture and inhibite mitosis in root tip cell. The chromosomal aberration rate of cells tended to be increased with increase of implanted ion dose. Compared with 60Co 7- rays, ion implantation induced lower rate of cells with chromosome aberration. However, there was a similary inhibitory effect on mitosis between ion beam and 7- rays. The electrophoretic banding patterns of peroxidase enzymes were altered by both mutagens and varied. Frequency of the chlorophyll mutation implanted by ion beam was higher than that induced by 7-rays. Mutation frequencies of heading date and plant height were similar between ion beam implanting and 7-rays irradiation.

C42.00

Pest and Disease Control

CNIC-01057 960067 CSNAS-0103 r, «) % ft ( mm.

STUDIES OF RADIOISOTOPE TRACER TECHNIQUE AND ITS APPLICA- TIONS TO PESTICIDE SCIENCES IN CHIN A/JIA Minghong CHEN Qing (In- stitute for Application of Atomic Energy, Chinese Academy of Agricultural Sci- ences, Beijing) ZHENG Ran (Institute of Chemistry, Henan Academy of Sci- ences, Zhengzhou) The improper use of chemical pesticides has resulted in serious environmental problems and food pollutions, affecting the ecosystem balance and human being health. There are more and more scientists and research institutions being engaged in the area of radioisotope tracer techniques for pesticide sciences in China. So far, 53 more than 80 labeled compounds, including insecticides, fungicides, acaricides, herbicides, metabolic intermediates, fertilizer and biological agents, etc have been synthesized at the laboratory for application of isotopes in Institute for Application of Atomic Energy, Chinese Academy of Agricultural Sciences. Over past several years, the great achievements have been made in the researches of radioisotope tracer techniques and their applications to pesticide sciences in China, especially in the researches for isotopic labeling, residues, degradation and metabolism of pesti- cides in plant and animal, behavior and fate of pesticides in environment, and tech- niques for safe application of pesticide, and so on. The researches of radioisotope tracer techniques and their applications to pesticide sciences in China in the past years are briefly introduced. Some problems are put forward and the development in future is predicted also.

C45.00 Other Applications of Radiations and Radioisotopes in Life Sciences

CNIC-01035 960068 SMC 0124 fitASttJllL'h«*£HKit# SZ-S1 «£ Fab ft&&*:M)ftW*&!m&/ mmm »K um^ vmm^U) m GMP-UO j£Mia<£ SZ-51 nT$ *0ja?f8f&, &m PCR irmrm

pHENl SZ-51Fab/Hu HiSicft , # PHENl-51Fab/Hu HB2151 +, & ELISA &£#$!]£ SZ-5lFab/Hu &&&&}% 500 Western $$&%ftiE&3!i£lW SZ-51 ®c^ Fab >tSfg##*^ GMP-140 4g£. CONSTRUCTION AND EXPRESSION OF A FUNCTIONAL MONOCLONAL ANTIBODY SZ-51 SPECIFIC FOR GMP-140 CHIMERIC Fab FRAGMENT IN ESCHERICHIA COLI/GU Jianming ZHANG Xiaomin XIA Lijun et al. (Suzhou Medical College) (In Chinese) The variable region cDNAs of a monoclonal antibody SZ-51 specific for a- granule membrane protein (GMP-140) on the surface of activated human platelets were spliced with the constant region cDNA of the heavy chain CHI and light chain K of human Ig G by means of the gene recombination techniques. The above recombinant gene was amplified by the polymerase chain reaction (PCR). The ex- pression vector of phage plasmid pHENl SZ-51 Fab/Hu was constructed. The 54 pHENl-51 Fab/Hu was introduced into non-suppressor E. coli HB2151. The amount of expression of SZ-51 Fab/Hu measured by quantitative ELISA was about 500 /ig/L. Western blot demonstrated that the SZ-51 chimeric Fab fragment could specifically bind to GMP-140.

CNIC-01079 960069 SMC-0127

THE ROLE OF RADIOACTIVE TRACING IN HEALTH PROTECTION/LU Anshan ZHU Shoupeng (Suzhou Medical College) (In Chinese) Application of radioactive tracers in health protection is introduced. The differ- ent radioactive tracers can be applied to the studies of many functions, including im- mune function , permeability of skin, metabolism of nutritional materials, uptake of aerosols, monitoring of internal contamination in the body, protection of organs by blocking, accelerating removal of internal contamination in the body, cell cyele, etc Generally, since the quantity of radioactive tracers required for tracing is exception- ally small, there in no interference with normal physiological function of the organ- ism. According to the different aims in health protection, the radioactive tracers can be used in a wide scope in order to promote the progress of health protection.

CNIC-01096 960070 CSNAS-0108 32

55 AVAILABILITY OF PHOSPHORUS FROM GROUND PHOSPHATE ROCKS FOR RAPE (Brassica napus L. ) /ZHU Yongyi YANG Juncheng CHEN Jingjian (Institute for Application of Atomic Energy, CAAS, Beijing) LIU Delin ZHU Zhaomin WU Ming (Institute of Atomic Energy, Hunan Academy of A- gricultural Sciences, Changsha) The availability of phosphorus from the ground phosphate rock, which is pro- vided by Kaiyang mining plant, Guizhou Province of China, is investigated in pot experiment with acid red soil for rape (Brassica napus L. No. 13 Xiangvou, Chinese Olive Group) by 32P indirect labelling method. The results show that the yield in- creased significantly by applying ground phosphate rock (GPR) and the efficiency of GPR is equal to 17. 1% of that from calcium superphosphate. It is calculated as that the fertilizer efficiency of 1 kg of calcium superphosphate is the same as that of 8- 53 kg ground phosphate rock in Guizhou Province of China. The effect on the grain yield is evaluated by pot and field microplot experiments, and it is found that the main effect is to increase the pod number. The fertilizer efficiency in field exper- iment is the same as that in pot experiment.

C50.00

HEALTH, RADIATION PROTECTION AND ENVIRONMENT

C52.00 Radiation Hazards and Environmental Safety Evaluations of Nuclear Installa- tions

CNIC-01039 960071 CiRP-0012 30

7 70-so

TRITIUM MONITORING FOR NUCLEAR FACILITIES AND ENVIRONMENT 56 IN CHIN A/YANG Huaiyuan (China Institute for Radiation Protection, Taiyuan) Reviews of achievement and great progress of tritium monitoring techniqes for nuclear facility and environment in China over the past 30 years are made which in- cluding the development experiences of several important detectors and instruments for health physics monitoring on site and some sampling and measuring methods for environmental monitoring and assessment. Information on nation wide survey activ- ities during 1970~1980 years on natural environmental radioactivity level in China and the related tritium data are given.

CNIC-01060 960072 iAE-0152

^.¥ (1990-1992) jsraraw 33450 0992^;

CONTINUOUS MONITORING IN THE ENVIRONMENT NEAR NUCLEAR FACILITIES/YUE Qinqyu XIAO Xuefu JIN Hua (China Institute of Atomic- Energy, Beijing) (In Chinese) Techniques and methods on continuous monitoring the 7 radiation dose rate due to the effluence from nuclear facilities with a high pressure argon ionization chamber have been described. About 33450 individual record data for three years (1990'—1992) have been obtained by a continuous monitor in the environment near the two reactors (15 MW heay water reactor and 3. 5 MW light water swimming pool reactor). These date have given the external dose caused by noble gas plume from the ractors. The maximum value of annual effective dose is 53. 8 fzSv in 1992, which is only equal to 9 % of natural background level. The monitoring results have compared with the computed results for the finite cloud atmospheric diffusion mod- els, and they are in agreement within 62%.

CNIC-01062 960073 SMC-0126 ttfelSftl + SyffiatffflSfcttflEaW/^ftE M^ ^^ ^ 57 #5 (Chashma) ^%X@^ 6 ^gPH 10 . uio £Xgft#AMHfifltfHiW 8060

A CLINIC TRAUMATIC EPIDEMIOLOGIC ANALYSIS UNDER THE P-300 PROJECT CONSTRUCTION/HUA Jinming WANG Zhongyuan FEI Jinhua (Suzhou Medical College) (In Chinese) The clinic traumatic epidemiology at the project of Chashma Nuclear Power Plant was investigated (the Project in Pakistan was contracted and built by China National Nuclear Corporation). The analysed cases were 8060 from 6 department, 10 types of work, 1410 persons of engineers and technicians. The rate of potential mortality and deformity in injury were 1.13% and 0. 57% ,respectively. The injury rate decreased with the increase of the age and the service length of occupation. The difference of injury rate between the types of work was significant; the steel lining team and nuclear island team had the highest injury rate. The serious injury might common occur in nuclear island team and arround the region of nuclear island site. The relation between injury rate and the progress of project was analysed;according to the occurrence of trauma, the suggestions of trauma prevention at project were offered as well.

CNIC-01068 960074 CSNAS-0105

1985 4f-*3 1987 ^MWAM&fctt^S 50 km

"2Th>238u>226Ra, J14. 16 Bq, M?£S;g0~lF.. 32 Bq; §&JfzK#1'& P ^*^J 1- 75-1148- 76 Bq, . 3Bq,

58 Jl 11-1-17. 8 Gyh"\ THE INVESTMENT OF RADIOACTIVITY BACKGROUND IN AGROENVI- RONMENT AROUND DAYA-BAY NPP/HOU Lanxing XU Shiming ZHAO Wenhu et al. (Institute for Application of Atomic Energy, Academy of Agricultur- al Sciences, Beijing) (In Chinese) The investigation of radioactivity and 7 absorbed dose rate in free air were tak- en in soil organisms water around Daya-Bay NPP 50 km radius in 1985 and 1987- The result shows that the difference of total radioactivity in soil in same soil section between up and down is few» but the diversity among soil points is big. The order of natural radionuclides in top soil is 40K>232Th>238U>226Ra. The diversity among soil point of 137Cs is very big (0~15. 32 Bq) and the average value is 4- 16 Bq. The total (3 activity in every kilogram water is 1. 75-— 1148. 76 Bq and the order is sea water>pond water>river water>spring water. The total (3 activity in every kilo- gram fresh organisms is 5- 2~903. 3 Bq and the order is rice straw>peanut kernel >peanut shell >rice hull> fish bone> leaf vegetables (green vegetable > romaine lettuce) >rice>meat (pork>chicken) > fish > milk > egg (duck's egg>layer's egg) >sugercane. The total a activity in every kilogram fresh organisms is 0. 05~ 283. 6 Bq and the order is rice straw>peanut shell>-fish bone>rice hull>peanut kernel>egg>leaf vegetables>rice>sugercane>meat>milk. The diversity of 7 absorbed dose rate in free air between in and out of house is 11. 1~17. 8 Gy • h~!.

CNIC-01076 960075 IAE-0154

« s i f ii i. &:?%mMi&i%&zhmum%tK£, si * as B # 10 nGy • h-'~10 mGy • h"1. JE«|*|)Ea3K«*cH*|SI#»X^ttl)6l5^. CONTINUOUS MONITORING SYSTEM FOR ENVIRONMENTAL Y RADIA- TION NEAR NUCLEAR FACILITY/JIN Hua YUE Qingyu WANG Wenhai

(China Institute of Atomic Energy f Beijing) (In Chinese) The continuous monitoring system which is used for the environmental routine 59 and accident emergency 7 radiation monitoring near nuclear facility is described. The continuous monitoring system consists of a high pressurized ionization cham- ber , integrated weak current amplifier, V/F converter and intelligent data recorder. The data gained by recorder can be transmitted to a PC through a standard RS- 232-C interface for the data handling and graph plotting. This continuous monitor- ing system has the functions of alarm over threshold and recorded output signal of detetor and temperature. The measuring range is from 10 nGy • h~' to 10 mGy • h"1 because a high insulation switch automaticly changed measuring ranges is used. The monitoring system has been operating continuously for a long time with high stability and reliability.

CNIC-01078 960076 QNPC-0003

MW

RESEARCH AND APPLICATION OF THE COMPUTER REAL-TIME DOSE ASSESSMENT SYSTEM IN QINSHAN NUCLEAR POWER PLANT/DUAN Xuyi XU Dongwu (Qinshan Nuclear Power Company,Hayan, Zhejiang) (In Chi- nese) The choice of assessment method and purpose of setting computer real-time dose assessment system is introduced, the system is one of the special emergency fa- cilities in QNPP (300 MW set). According to the environmental characteristics around Qinshan Nuclear Power Plant, the dynamic puff model to emulate the con- tinuous plume and three dimensions wind model are choiced. It describes the model and parameters of computer real-time dose assessment system (CRTDAS), the composition and development of the hardwares and softwares, the assessment pro- gresses , and main functions. It includes: acquiring and displaying of meteorological parameters, environmental radiation parameters and plant safety parameters, de- 60 scribing the plant status and estimating accident sources terms, assessing the envi- ronmental consequency et. al. Finally, the applications of the assessment system, emulating calculations, practices and some developing aspects are also introduced and some rational proposals for the next development in the field are put forward.

CNIC-01101 960077 CIRP-0016 ttiftJt$F**i¥ffr&ftfc (NGLAR) /fe jft

(NGAS*PNACCK

IBM S^^W 386

A PACKAGE FOR ENVIRONMENTAL IMPACT ASSESSMENT OF NUCLEAR INSTALLATIONS (NGLAR) /YANG Yin CHEN Xiaoqiu DING Jinhou et al. (China Institute for Radiation Protection, Taiyuan) {In Chinese) The main contents, designing strategies and properties of the microcomputer- based software package NGLAR are described for environmental impact assessment

of nuclear installations. The package consists of the following components: NGAS &•- NACCthe codes for routine and accidental airborne releases respectively; NLIQ, the code for both routine and accidental liquid releases; and NRED, environmental database system of nuclear installations. NGAS &- NACC are used for evaluating at- mosphere dispersion and doses to public of radioactive materials released from nu- clear facilities, giving the concentrations around the facilities of radionuclides in air, on ground surface, and in varieties of animal foods and farm produces, and further estimating collective doses and doses to critical group around the facilities. NLIQ is suitable for liquid effluence released to non-tide rivers, and is modelled to calculate firstly the concentration of radionuclides concerned in the polluted rivers, and then to estimate the resulting doses to public. Under routine releases, the doses obtained from NGAS and NLIQ can be appropriately categorised and summed up together. 61 NRED can be run independently, also used to provide some input data for above programs and save data permanently for them. Having both English and Chinese versions, the package, which was fabricated of multiple functions can be run on IBM 386 or higher and its compatible microcomputers.

CNIC-01118 960078 mmm.

4»B*tmCs £«5Fi£*fif*7#J§Fft&^ I960 ^. 30 £*£*, 4>S*t137Cs

A REVIEW: STUDY ON THE BEHAVIOR OF 137Cs IN AGRICULIURAL ENVI- RONMENT OF CHINA/ZHU Yongyi YANG Juncheng CHEN Jingjian (Insti- tute for Applications of Atomic Energy, CAA.S, Beijing) (In Chinese) In China , study on the behavior of 137Cs in agricultural environment was begun in 1960. Many papers on the behavior of 137Cs in soil-plant system and the estima- tion of 137Cs radioactivity in soil and food were published. The absorbtion, accumu- lation and distribution of 137Cs in plant , the relationship between absorption of 13? Cs by plant and contaminating way and form,the 137Cs radioactivity in soil and food and its transfer coefficient in soil-plant system, the effects of the characters of soil and plant as well as the living stages on the transfer are concerned. The results show that the average radioactivity of 137Cs in soil of China is 10. 45 Bq/kg,and the deposition densities decrease with the latitube decreasing. The transfer coefficent of 137Cs from soil to the agricultural products is about 0. 12~8. 19 X 10~3. The distri- bution of 137Cs in rice plant is in the order of the root>glume>leaf!>stem!>rice. The radioactivity of aerial part accumulates mainly in the glume. The countermea- sures to alleviate the adverse effects of 137Cs contamination need further study.

62 C53.00 Radiation Protection Standards

CNIC-01053 960079

PROTECTION, MONITORING,MANAGEMENT AND EVALUATION ON THE PRACTICE FOLLOWING THE NUCLEAR AGRICULTURE/YANG Juncheng CHEN Jingjian ZHU Yongyi et al. (Institute for Application of Atomic Ener- gy, CAAS, Beijing) (In Chinese) Following the development and application of atomic energy for peaceful pur- poses in the past 30 years, a cross scientific course called nuclear agriculture has been established in China. On the basis of national laws of radiation protection, the management and monitoring results of radiation practice at the Institute for Appli- cation of Atomic Energy, CAAS for 1964~1994 have been summarized and ana- lyzed. It is shown that there is no affection to the environment by the practice of nuclear agriculture under normal conditions. The results will provide an important scientific base for the evaluation on the radiation safety of the environment and pro- mote the prosperity of the course.

C54.00

Radiation Protection Procedures

CNIC-01127 960080 FRDINI-0013

63 THE DEVELOPMENT OF NON-SEPARATION HEPA FILTER IN NUCLEAR FIELD/YANG Jing KONG Qingqi SHI Zexuan (The Fifth Research and De- sign Institute, CNNC, Zhengzhou) {In Chinese) At present, to lower the operation cost of cleaning equipment and to reduce the solid waste amount are urgent tasks for the air cleaning system in nuclear facilities. In order to meet this demand a new type air cleaning equipment, non-separation HEPA filter (high efficiency particulate air filter) ,has been developed. The peculiar- ity of this non-separation HEPA filter, the developed status in China and abroad as well as some key issues are systematically summarized in the article.

C55.00

Personnel dosimetry and Monitoring

CNIC-01092 960081 SMC-0128 A d^s«, mm

PRO For WINDOWS

STUDY ON THE STATISTICAL DESIGN FOR THE HEALTH EVALUTION OF STAFFS OF THE NUCLEAR INDUSTRY IN CHINA OVER THE PAST 30 YEARS/ZHANG Husun CHENG Yiling ZHOU Liren (Suzhou Medical Col- lege, Suzhou) (In Chinese) In order to scientifically and objectively evaluate the health and the risk of ura- nium miners, and the workers involved in radiation, chemical and poisonous sub- stances and not contacting staffs of the nuclear industry in China over the past 30 years. A statistical test program have been developed according to computer CPU, and with FoxBASE+ and FoxPRO For WINDOWS. The program may be used to test their health and risk instend of previous transmition of data with the help of the high level computer language and operation analysis, and the actual work effi- 64 ciency has been greetly raised. As regard to the program design of database, fault- tolerant function, array and macro-substitution technique and Rushmore technique have been established besides setting 130 indexs in 4 large databases and linking the databases with the numbers of the staffs. Therefore, computer algorithm are speed- ed up.

C60.00

RADIOLOGY AND NUCLEAR MEDICINE

C64.00 j Radioisotopes in Therapy

CNIC-01116 960082 SMC-0130 Y8 T m (^ 4 h 51Cr YS T . (1) XG-7, K562, Daudi, U937,

TNF, (6) (HSP)

STUDY ON THE MECHANISM OF KILLING TUMOR CELLS BY Y5 T CELLS USING 51Cr AND 3H TECHNIQUE /ZHANG Xueguang LI Xingan XIE Wei et al. (Suzhou Medical College, Suzhou) (In Chinese) The molecular mechanism of recognizing and killing tumor cells by 78 T cells was analyzed. The experiment results were as follows: (1) YS T cells could recog- nize and mediate strong cytotoxic activity to different tumor cells including XG-7, K562, Daudi, U937 and Jurkat? (2) YS T cells showed strong cytotoxic effect on freshly isolated autologous and allologous leukemia cells; (3) No cytotoxic activity to normal cells could be observed; (4) Cytokines such as IL-4 and TNF could work in coordination with 78 T cells to increase the cytotoxic effect; (5) 78 T cells could 65 secret high levels of IL-2, TNF and Y-IFN; (6) Anti-HSP70 monoclonal antibody could block the cytotoxic activity of 7§ T cells against XG-7-

D00.00

ISOTOPES, ISOTOPE AND RADIATION APPLICATIONS

DIO.OO

ISOTOPES AND RADIATION SOURCES

D13-00 Other Isotope Production, Separation and Enrichment

CNIC-01119 960083 SINRE-0071 (HFETR)

HFETR

ACTIVITY CALCULATION OF RADIOISOTOPES IN HFETR/LIU Shuiqing (Nuclear Power Institute of China, Chengdu) (In Chinese) The activity calculating method and formulas of seven kinds of radioisotopes for High Flux Engineering Test Reactor (HFETR) are given. The perturbation of targets to neutron fluence rate is considered while targets are put into the neutron fluence rate field of reactor core. All perturbing factors of seven kinds of radioiso- topes being used in HFETR are presented. After considering the perturbation, the calculating accuracy of radioisotope activity has been raised 10%. The given method and formulas have ended the history of all activities estimated by experiences, ex- cept for that of 60Co, in the radioisotope production of HFETR. The conclusions are 66 also useful and instructive for the production of radioisotopes in HFETR.

D20.00

ISOTOPE AND RADIATION APPLICATIONS

D24.00 Advances in Tracer Techniques

CNIC-01029 960084 LMPI-0004

SUITABLE ACTIVATED CARBON-13 TRACER TECHNIQUES/ZHANG We icheng PENG Xiuru WANG Yuhua (Institute of Modrn Physics, Academia Sinica, Lanzhou) Feasibility and applicability studies of the proton induced gamma ray emission (PIGE) have been performed. The graphite was first bombarded at various proton energies to determine gamma ray yield (and, thus, sensitivities) for the reaction of interest. The accuracy for the determination of 13C abundance was checked, and the precision with which this value and ratios 13C/12C may be obtained was estab- lished , by repetitive analysis samples. The performance of different standards in this determination was assessed. The mathematical treatment was developed for the determination of 13C abundance in tracer studies, and to derive the equations that govern this method of analysis from first principles, to arrive finally at a sim- ple expression by virtue of the observed regularities. The system was calibrated by measuring the gamma ray yield form the 12C (p, 7) 13N and 13C (p, 7) 14N reaction as a function of known 13C enrichment. Using this experimentally determined cali- bration curve, unknown materials can be assayed. This technique is applicable to 67 the analysis of samples with 13C enrichments between 0. 1% and 90%. The sam- ples of human breath natural samples were analyzed against graphite and Cylinder

CO2 standards. Relative standard deviations were

E00.00

ENGINEERING AND TECHNOLOGY

E10. 00 X@

ENGINEERING

Eli. 00 Thermodynaimics and Fluid flow

CNIC-01048 960085 BINE-0029

VOLUMETRIC EXPANSION COEFFICIENT AND COMPRESSIBILITY OF WATER AND STEAM/LUO Bangqi (Beijing Institute of Nuclear Engineering) (In Chinese) 68 Volumetric expansion coefficient and compressibility of water and steam are important parameters usually applied in the reactor thermal hydraulic, heat transfer and engineering thermodynamics. The formulas of these coefficients have been de- rived from Gibbs free enthalpy and Helmholtz free energy. The derivation of volu- metric expansion coefficient and compressibility formulas is meaningful for solving the practical application problems of the thermal hydraulic, heat transfer and engi- neering thermodynamic. These parameters of water and steam can be directly used to calculate the fluid temperature and pressure in the nuclear reactor thermal hy- draulic analysis. In the calculation for the fluid temperature and pressure» using the formulas of these coefficients mentioned above can save the calculation time and computer memory, speed up the nuclear design process and avoid the interpolation errors compored to using the equation of mass, energy and momentum. That is of great importance to raise the safety and economy of the PWR design.

CNIC-01122 960086 SNERDI-0032 tefcr&ftSit+TKffltt* (*«) M#«/flH£ *£0S <±.M

ANALYSIS OF WATER SLUG (WATER HAMMER) IMPACT IN STEAM PIPES OF NPP/ZHOU Meiwu DONG Xiankang (Shanghai Nuclear Engineering Research and Design Institute) {In Chinese) A severe water hammer may be happened if water entrapped in steam pipe. Consequently, pipe or its components and restraints could be damaged and its func- tion may be lost. This kind of water hammer is a potential danger to safe operation of power plants, especially to nuclear power plants. The process of forming a water slug and calculating method of impact force for water slug on the piping bend are presented, and an example is also given by using this calculating method.

E13-00 Structures and Equipment

69 CNIC-01129 960087 ECBGE-0003 ft,

THE STUDY OF THREE-DIMENSIONAL NET METHOD OF DEFORMATION OBSERVATION/WU Jingqin (East China Bureau of Geology, Nuclear Industry, Nanchang) {In Chinese) Due to the influence of all kinds of factors, when buildings and equipments of nuclear power stations, water power stations and so on are in their service, deforma- tions always happen to them. Especially, the breakage, the slide of edge danger rocks and basic displacement in the area of nuclear power station site can all inter- fere its regular operation, even endanger safety. But the traditional trigonometric net control can not obtain high precise deformation observation. So, topographic balanced vertical deviations are applied. The slope distance is devided rationally into horizontal and vertical components, then the precise vertical component is used to participate in restricting the deflection on order to enhance the observation post's precision. Meanwhile, the element model is selected, high precise monitoring net of three-dimensional deformation is set up, using astro-geodetic deflection of the vertical to correct the observation values. In this way, the earth error of height is given, the plane coordinate is defined by paralleling some plane of reference ellip- soid. This method may satisfy the deformation observation in the projects such as nuclear power stations or so.

E16- 00 Accelerators

CNIC-01094 960088 IAE-0156 70 mm, £ 0. 05 mm, fS&&(fe&&J?£*t 1-4 MeV

Gy/min H*. feMfcrtfeift;*^ 0. 55 I^±IE1E-*AhW5W*¥/>;f 4. 15 Gy/min Itf, g^^/J^ 1%, 700V, fl*£«)*)+*J»EiJ*2X10! Gy/min H*. Kg^RjE/hT 1. 5%. ^£ o. £

A SEALED PENETRATING IONIZATION CHAMBER WITH THIN WINDOWS OF LARGE DIAMETER/GUAN Xiufen CHEN Wenkui WANG Guobao et al. (China Institute of Atomic Energy, Beijing) A penetrating ionization chamber can be used in a raphytron (a radiographic linear electron accelerator for non-destructive testing) to monitor the output dose and dose rate of an accelerator and to provide monitoring and control signals for dose protection, but its existence less affects the output characteristics of the accel- erator. Its linearity and long-term stability are two keys in regulating, testing and operating of an accelerator. A double casing sealed structure is used in the ionization chamber with thin windows of large diameter. The fabricating technology of the chamber is extremely difficult due to its strict limitation. The penetrating perfor- mance is better owing to the use of thin windows of 80 mm in diameter and 0. 05 mm in thickness. The total thickness of its thin windows and plate electrodes is so chosen that the absorbing intensity should be less than 1 % to the X-ray beam in the energy from 1 MeV to 4 MeV. When a dose rate is 1 Gy/min on the central ax- is at 1 meter from the target of an accelerater, the sensitivity is high and the ioniza- tion current is larger than 0. 55 (J.A. It has good linearity and saturation characteris- tics. The nonlinearity is less than 1 %, when a dose rate is less than 4.15 Gy/min on the central axis at one meter from the target of an accelerator. When pulse dose rate borne by the chamber is near 2 X 105 Gy/min and the working voltage is at — 700 volts, the recombination correction is less than 1.5%. It has good repro- ducibility too. The reproducibility of ionization current of the chamber has been 71 measured twice in an interval of nineteen months, and the results were all the same about 0. 5%. The leakage current of the chamber is less than 10~13 A, when the working voltage is —700 volts. The chamber has been working steadly and reliably for a long time under the conditions of adverse circumstances and strong interfer- ence as well as the existence of movement and shock.

E20.00

FISSION REACTORS (GENERAL)

E22.00

Reactor Components and Accessories

CNIC-01031 960089 SNERDI-0028

K,

CALCULATION AND TEST OF STRESS INTENSITY FACTOR FOR INSIDE CORNER CRACK OF NUCLEAR VESSEL NOZZLE/WANG Baisong XU Dinggen (Shanghai Nuclear Engineering Research and Design Institute) Nozzle is an important structural type of nuclear pressure vessel. The stress intensity factor (SIF) Ki for inside corner crack of nozzle under internal pressure is an important basis for fracture evaluation of this region required by code. An im- proved 3-D 20-node isoparametric singular element with quater-points and displace- ment method are used to calculate SIF K i and its variation and distribution for in- side corner crack of nozzle. The relationships between K \ and geometric parame- ters of crack and structure are analyzed. The results are coincide with those ob- 72 tained from 3-D photoelastic test. On the bases of calculations and analyses as above, the simple and conservative formulae calculating SIF K\ for inside corner crack of nuclear vessel nozzle under internal pressure are obtained. These formulae are verified by 3-D photo-elastic test and can be used in engineering.

CNIC-01040 960090 SNERDI-0029

u

SEISMIC RESPONSE ANALYSIS AND TEST FOR HEAT EXCHANGER OF NUCLEAR POWER PLANT/XU Dinggeng YE Weijuan WANG Jixing (Shanghai Nuclear Engineering Research and Design Institute) Seismic response analysis and tests for three typical types of heat exchangers, i. e. vertical straight tube one, horizontal straight tube one and vertical U-tube one have been done. Additionally, modal tests have been carried out for horizontal tube bundle and U-tube bundle. Acceleration, displacement and strain response from seismic tests for all main parts of the three types of heat exchangers were measured under both conditions with and without water. Structural free vibration characteri- zation and seismic response are calculated by means of tube-beam mathematical model of finite element method. Calculation results fairly meet test data. Thus effec- tiveness of the mathematical model is further verified.

CNIC-01081 960091 SNERDI-0030

73 MECHANICAL ANALYSIS OF STRUCTURAL INTEGRITY AND RESEARCH ON SITE MEASUREMENT FOR THE RPV OF QINSHAN NPP/QU Jiadi DOU Yikang HE Yinbiao et al. (Shanghai Nuclear Engineering Research &- De- sign Institute) (In Chinese) To perform a complete mechanical analysis for ensuring the comprehensive be- haviour of structural integrity of RPV, the first is to establish a completeness con- cept. The completeness for stress analysis should at least include four contents, they are the complete operating condition and loading assembling, the complete structure and interfaces, the complete failure criteria of function and the complete stress lim- its. Then from dissecting the loading system of RPV 3 kinds of undetermined load can be found, these are stud-bolt, temperature and piping loading, besides, in order to knowing the conservative margin of design loading, it is necessary to perform the actual measurement and monitor for the loading spectrum. As the first step of im- plementation , the stud-bolt loading under hot transient has measured at the Qin- shan NPP site. In order to checking the analytical results, during primary system hydrostatic test, the strain and displacement measurements are arranged for RPV. In the finished analytical works, these include loading assembling, transient stress analysis, fatigue analysis, fracture calculation, earthquake calculation, thermal shock consideration, interface parts analysis and determing of P-T limits etc. , that ex- pounds and proves the structure integrity of RPV from mechnical respect. Finally, the actual proving obtained by site measurement indicates the limits and evaluations given by soft ware system are reasonable.

CNIC-01105 960092 SNERDI-0031

, TASC

FLOW-INDUCED VIBRATION TEST AND ANALYSIS OF HEATEXCHANGER 74 IN NPP/YANG Renan YAO Weida WANG Jixing (Shanghai Nuclear Engi- neering Research and Design Institute) (In Chinese) A method of comparing the results of calculation with test is used to verify the reliability and adequacy of the program in order to evaluate the flow-induced vibra- tion of heat-exchanger tubes, so the program can be applied to design of safety re- lated heat-exchanger in NPP. The shell side flow velocity and tube vibration are measured. The results of measurement show that there is a margin of safety in gen- eral for the results of calculated by program TASC and PIPO 1, but it should be noted that the flow velocities may be higher at a few points of the shell side.

E24.00 Reactor Control Systems

CNIC-01120 960093 SINRE-0072

(4X4-4) m^mnjtimmzi&wimrTtf) 40

A MODIFICATION DESIGN AND ADJUSTING TEST FOR INSTRUMENTS AND CONTROL SYSTEM OF CRITICAL ASSEMBLY/WU Manrong LI Guangjian (Nuclear Power Institute of China, Chengdu) (In Chinese) A more reliable and safe control system and it' s instruments for HFETRCA (high flux engineering test reactor critical assembly) have been built. In the system high performance CMOS unit was used, which has high integration, strong anti- interference and high trigger threshold. In the design of control rod driving circuit, the speed negative feedback principle was applied that results in more stable rotat- ing rate of motors of transmission mechanism and more flexibility of adjusting rod speed. In order to improve reactor safety in accident, additional control circuit is e- 75 quipped, by which not only control rods with electromagnet will rapidly drop but al- so other control rods will insert at the speed of 2~6 times faster than the normal inserting speed. The key technique in the adjustment and new method of anti-inter- ference are also introduced. After more than 40 times physical experiments with (4X4 — 4) fuel element in HFETRC, it is proved that the design and adjustment of the system is success and they can be used as a reference to others.

CNIC-01036 960094 SINRE-0059

mm. DIGITAL REACTIVITY METER/JIANG Zongbing (Nuclear Power Institute of China, Chengdu) (In Chinese) The importance and the usual methods of reactivity measurement in a nuclear reactor are presented. Emphasis is put upon the calculation principle, software and hardware components, main specifications, application, as well as the features of the digital reactivity meter. The test results of operation in various reactors shown that the meter possess the following features; high accuracy, short response time, low output noise,high resolution,wide measuring range,simple and flexible to oper- ate, high stability and reliability. In addition, the reactivity meter can save the mea- suring data automatically and have a perfect capability of self-verifying. It not only meet the requirement of the reactivity measurement in nuclear power plant, but also can be applied to other various reactors.

CNIC-01103 960095 HYIT-0004 PH)

AS*

76 BASIC RESEARCH ON HUMAN RELIABILITY IN NUCLEAR POWER PLANTS/ZHANG Li DENG Zhiliang (Central-South Institute of Technology, Hengyang, Hunan) Human reliability in nuclear power plants is one of key factors in nuclear safety and economic operation. According to cognitive science, behaviour theory and er- gonomics and on the bases of human cognitive behaviour characteristics, perfor- mance shaping factors, human error machanisms and organization management, the project systematically studied the human reliability in nuclear power plant systems, established the basic theory and methods for analyzing human factor accidents and suggested the feasible approaches and countermeasures for precaution against hu- man factor accidents and improving human reliability. The achievement has been applied in operation departments, management departments and scientific research institutions of nuclear power, and has produced guiding significance and practical value to design. operation and management in nuclear power plants.

E30.00

SPECIFIC FISSION REACTOR TYPES AND THEIR ASSOCIATED PLANTS

E32.00 Power Reactors, Non-Breeding, Light-Water Moderated, Non-Boiling Water Cooled (PWR, ect. , Types)

CNIC-01065 960096 SINRE-0063 ft

TPLIB-95 #}mm&. TPLIB-95

ffl 5 ^mmSJffBJ®. -ffiffi#i££:ft:*l|fi#$i&KA&fSlllj 300 MW

77 w,

15XKT7L. MACRO TESTING FOR GROUP CONSTANT LIBRARY TPLIB-95/YAO Dong ZENG Daogui LIU Jingbo et al. (Nuclear Power Institute of China, Chengdu) LI Huiyun (Research Insititute of Nuclear Power Operation, Wuhan) (In Chinese) A macro test of the group constant library TPLIB-95 was introduced. The TPLIB-95 is an updated group constant library created by china Nuclear Data Cen- ter for LWR fuel assembly calculation program package TPFAP based on the JENDL-3. 1 evaluation nuclear data library. The calculations and analyses were carryed out by using five thermal reactor benchmark issues, a set of PWR zero- power critical experiments, the first cycle reactor core of 300 MW Qinshan NPP as well as the first cycle reactor core of 900 MW Daya Bay NPP. The calculation re- sults for the thermal reactor benchmark issues showed that the maximum deviation between the calculated and measured values for spectrum indexes is large, like 28 6-7% for p of BAPL-2. However, the maximum deviation for keu is only 0. 29% for TRX-2- The calculation results for zero-power critical experiments showed that the calculated value of Ka obtained by using TPLIB-95 is closer to the measured value compared with the one obtained by using the original library TPLIB. The agreement between the calculated and measured values for critical boron concentra- tion in the first cycle reactor cores in Qinshan NPP and Daya Bay NPP is quite good. The maximum deviation for the critical boron concentration is only 15 X 10-VL.

E36-00 Research, Test and Training Reactors

CNIC-01052 960097 SIP-0090

ffi£ MS FDKR n^f&Wi%m AF-DCDLIB, 78 FEB (Fusion Experimental Beeder) & & $ if ^ ?& ft ;"* #J . $1$:/* £ JC

150 MW BHP 5. 74 X 10'" B<, 8 3 8.34 MWK 4.08X10 km : FEB M CFR61

iu PWR J ACTIVATION CALCULATION AND ENVIRONMENTAL SAFETY ANALYSIS FOR FUSION EXPERIMENTAL BREEDER (FEB) /FENG Kaiming (South western Institute of Physics, Chengdu) Using an activation calculation code FDKR and decay chain data library AF- fX'DLIB to calculate the radioactivity, decay heat, dose rate and biological hazard potential (BHP) from activation products, actinides and fission products, in a Fu- sion Experiment Breeder (FEB). The code and library are introduced briefly, and calculation results and decay curves of related hazards after one year operation with 150 MW fusion power are given . The total radioactivity inventory, decay heat and BHP are 5. 74 X 1 02" Bq 8- 34 MW and 4- 08 X 10* km3 of air, respectively. at shut (luwri. Results obtained show that the first wall of FEB can meet the nuclear waste disposal criteria for the NRC 10 CFR61 Class C after a few weeks from shutdown. The inventory of important actinides for the fuel reprocessing, such as J>'l" and 1 Np were also calculated. It was shown that their concentrations do not excess the limit value of environmental safety required.

Production, Irradiation and Materials Testing Reactros

CNIC-01121 960098 SINRE-0073 HFETR 80

SO ±, . HFETR 500

79 , HFETR 80 ^7uf^li^^¥W60Co [^fi^^M±giD 380 THE STUDY ON 80 FUEL ASSEMBLIES CORE FOR HFETR/SUN Shouhua WU Yinghua BU Yongxi et al. (Nuclear Power Institute of China, Chengdu) The performance of 80 and 60 fuel assemblies cores for High Flux Engineering Test Reactor (HFETR) has been compared by theoretical analysis and operating results. These results show that the core performance of 80 fuel assemblies is the same as that of 60 fuel assemblies in the following aspects; the permission power of core, the irradiation test of materials, the transmutation doping of single crystalling silicon,the production of Mo-Tc isotopes,etc. The core of 80 fuel assemblies is more convenient in operation after 500 kW test loop installed, and in greatly raising the production of 60Co source with high specific radioactivity and the usage of fuel. As compared to the production of 60Co source of 60 fuel assemblies core, the benefit of 80 fuel assemblies core can increase more than 3. 8 millions yuan per year.

E40. 00

INSTRUMENTATION

Particle and Radiation Detection and Measuring Instruments and Methods

CNIC-01038 960099 UHMPH-0010

; (2) te££Wftj*^«t£1fc«Si]M*f*Y-M§#3l*ffi,KMi£#. (3) £ 5ooc, 8/MttiM*Jftj£itf, tf£MM*MttJ£fi&i&*itfiH]M$fl:> (4) &ffimmMMM'ti

700c, 3 /h^wii^c^ftT. "j&^mm^mm'&itMi'b, #jL¥flcg7&M*r*f-. ^*. mtfj£$LM., S^M TL . ii-^*-% D.J.Huntley et al. (1988) l#IIJW^*^i^^l^o THE EFFECTS OF PREDOSE AND ANNEALING TEMPERATURE ON SOME 80 DOSIMETRIC PROPERTIES OF THERMOLUMINESCENCE OF QUARTZ/ LIN Zhikai (Laboratory of Industrial Hygiene, Ministry of Health, China, Beijing) Yoshikazu KUMAMOTO Yutaka NODA (National Institute of Radio- logical Sciences, STA, Japan) The following aspects of dosimetric properties of quartz sample were studied. (1) The changes in dosimetric sensitivity of quartz with different predoses under different annealing temperatures; (2) The option of optimal annealing temperature which can make the dosimetric sensitivity of quartz to restore its original level; ( 3) The changes in dosimetric sensitivity of quartz with different annealing time at 500 C for 8 h; (4) Repeated experiments were carried out in order to prove whether the sensitivity of quartz can restore its original level at annealing tempera- ture 700 C for 3 h. It has been found that at 700 C for 3 h gave the least sensitivi- ty change and the sensitivity of quartz almost restored its original level. Repeated experiments with four kinds of quartz sample confirmed this conclusion. The dra- matic change of TL glow curve occurred only at the condition of annealing tempera- ture 900 C for 1 h. This result was different from that obtained by D. J. Huntley et al. (1988).

CNIC-01043 960100 SINRK-OO62

5>f/i.

COMPUTER BOARD FOR RADIOACTIVE-RAY TEST/ZUO Mingfu (Nuclear Power Institute of China, Chengdu) (In Chinese) The present status of the radioactive-ray test system for industrial applica- tions , the newly designed computer board for overcoming the shortcomings of the current system are described. The functions, measurement principles and the feature of the board as well as the test results for this board are discussed. The board puts 81 together many functions of the radioactive-ray test system, such as energy calibra- tion, MCS, etc. It also provides many other subordinate practical functions such as motor control, ADC and so on. The board summarizes two sets of test parts into one and therefore composes a powerful unit for the system. Not only can it replace all units in a normal test system for signal analysis, signal process, data manage- ment , and motor control, but also can be used in more complex test systems, such as those for double source/double energy/double channel testing, multichannel test- ing, position testing and core positioning, etc This board makes the test system more easily to achieve miniaturization, computerization goals, and therefore im- proves the quality of the test and reduces the cost of the system.

CNIC-01058 960101 iAE-0150

0. 95 mm, m##£JH4#T 0. 2% . mtPs HI-13 ^'JtOUfSi: - W 66 MeV l2C 5 0. 33X10 Pa, «m{£2#S?;fcl.3min; Mt irj IB * M £ A£ , *|&ffi£ £r

m, ijc#i!ca'^M, LIGHT-HEAVY ION FOCAL PLANE DETECTOR SYSTEM FOR Q3D SPEC TROMETER/WAN Yude LI Zhongzhen CHEN Yehao (China Institute of Atomic Energy, Beijing) A light-heavy ion focal plane detector system (500 mm in length) has been developed for the Beijing Q3D magnetic spectrometer. It has passed in-beam test and is already in use in nuclear physical experiments. The telescope of this detector system consists of 4 rectangular proportional counters and an ionization chamber.

The working gas is 70%Ar+30%CH4. The desk experiment shows that the in- trinsic resolution of the position-sensitive detector is about 0. 95 mm and the inte- grated nonlinearity is better than 0. 2%. The HI-13 tandem accelerator of China Institute of Atomic Energy experiment shows while under the pressure of 0. 33 X 105 Pa with 66 MeV 12C beam, the intrinsic position resolution has been measured to be about 1. 3 mm,and the energy resolutions for the energy loss AE ,the residual 82 energy Er and the total energy E have been measured to be 5-6%, 7. 1% and 3-7%, respectively. 2?A1 (12C, X) reaction is used to study particle identification and it is found that 13C and 12C can be separated completely.

CNIC-01095 960102 iAE-0157

(Gd2o3)

(2) DU (EU) (3)

(4)

APPLICATION RESEARCH OF NEUTRON COINCIDENCE COLLARS/QIAO Shengzhong (China Institute of Atomic Energy, Beijing) Experiments have been carried out to calibrate the neutron coincidence collar and to understand the effects produced by the depleted uranium (DU) rod distribu- tion in pressurized water reactor and boiling water reactor fuel assemblies, assembly positions, and the change resulted from the adding of cadmium, cardboard and

plastic, burnable poison (Gd2O3) rods and so on. The results of the experiments

show that: (1) The coincidence count rate decreased progressively when the dis- tance from the source to the assembly was increased, however, when the assembly was moved beyond a certain position, it began to increase. (2) The deviation of the coincidence count rate could be as large as about 7-5% for different DU rod distri- butions in the PWR assembly, while this value changed to 7 % ~ 9 % when the same number of EU rods were used with different loading configurations in the fuel assembly. (3) When Cd liners were used, the contribution of epicadmium neutron would be larger; otherwise, the contribution of thermal neutron would be larger. The coincidence counting efficiency was increased when cardboard and plastic were added. (4) The coincidence count rate decreased with increasing number of poison rods; however, the decrease of the coincidence count rate would be less if Cd was used. The measurement precision of the coincidence count rate for PWR and BWTR 83 without Cd liners was less than 0. 5%; otherwise, it would be less than 1%.

CNIC-01099 960103 ciRP-0015

<1Am, 238U,

ADC

. 9999, g CALCULATION OF GEOMETRY FACTORS USING OVERLAPPING AREA METHOD AND EXPERIMENTAL VERIFICATION/SHI Zhixia ZHANG Aim ing (China Institute for Radiation Protection,Taiyuan) Yuuji Minowa (Oarai Re- search Establishment of JAEARI) (In Chinese) The calculation of geometry factors under special conditions through a method based on the overlapping area of the source and the projection of the detector and experimental verification are introduced. The experimental verification was done in Oarai Institute of Japan Atomic Energy Institute under Japan STA Scientist Ex- change Program. The sample chamber can be pumpped and the distance between sample disk and detector is accurately adjustable. Semiconductor detector with the area of 450 mm2 and alpha standard sources 241Arn,238U,233U,239Pu and 244Cm were used for experiment. After the recalibration for the indication and actual separation between sample disk and detector, the activity of 241Am source and the ADC zero point of multichannel, calculation values conform with experiment within 6%. When sample chamber is not vacuum, the experimental verification of geometry fac- tors affected by alpha range is done with 2000 mm2 detector, and the theoretical values meet the experimental values very well after the revision of discriminating threshold and the thickness of detector windows. The relative coefficient is about 0. 9999 and there aren't significent differences after X2 and F check.

84 CNIC-01106 . 960104 IAE-0160

GM

1 & assxio-'-i. ssxio-oc-kg-'-h- , RPRM*****^. 58 c-kg-> •h"1, .6tt»>10»«, JSfflT-30-C~50-C5f^MSo STUDY ON DOSIMETRIC CHARACTERISTICS OF MICRO GM COUNTERS/ CHEN Changmao ZHU Junju (China Institute of Atomic Energy, Beijing) (/« Chinese)

In the cylindric Ne-Br2 filling micro GM counters, the influence of the struc- ture parameters and use conditions on dosimetric characteristics is studied. The ex- periments showed: (1) the secondary pulse series following the primary pulse is a root cause to shorten plateau; (2)the plateau slope is chiefly originated from the ad- dition of counting pulses formed by any space between counter electrodes; (3) the filling gas pressure has a significant effect on 7 photon sensitivity in the micro coun- ters. With a resistance of suitable value at the wire end of anode, the stray capaci- tance of counter will be decreased, so that the plateau becomes long and plane, the start voltage is reduced, the dead time is shortened and the measure range then is widened. Several experimental counters with different sensitivity and measure range have been designed. The plateau length is greater than 80 V (slope

CNIC-01110 960105 SINRE-0068

85 THE DEVELOPMENT REPORT OF AN INTELLIGENT NEUTRON FLUENCE INTEGRATION MONITOR/JIANG Zongbing WEI Ying (Nuclear Power Insti- tute of China, Chengdu) {In Chinese) An intelligent neutron fluence integration monitor is introduced. It is used to measure the received neutron fluence of the monocrystalline silicon in reactor radia- tion channel. The significance of study and specifications of the instrument are briefly described. The emphasis is on the working principle,structure and character- istics of the instrument. The instrument is intelligent due to use of monolithic mi- crocomputer. It has many advantages proved in the actual practice, such as powerful function, high accuracy, diversity of application, high automatization, easy to oper- ate, high reliability, etc. After using this instrument the monocrystalline silicon radi- ation technology is improved and the efficiency of production is raised.

E42-00 Other Nuclear Instrumentation and Methods of Measurement

CNIC-01072 960106 IAE-0153

CENTRONICS ^^ , is?

±2.3%, ±0.3%8.±1.9%. INTELLIGENT TYPE SODIUM INSTRUMENTATIONS FOR LMFBR/CHEN Daolong (China Institute of Atomic Energy, Beijing) The constructions and performances of a lot of newly developed intelligent type sodium instrumentations are described. The graduation characteristic equations 86 for corresponding transducer using the medium temperature as the parameter are given. These intelligent type sodium instrumentations are possessed of good lineari- ty. The accurate measurement data of sodium process parameters (flowrate, pres- sure and level) can be obtained by means of their on-line compensation function of the temperature effect. Moreover, these intelligent type sodium instrumentations are possessed of the self-inspection, the electric shutoff protection, the setting of full- scale, the setting of alarm limits (two upper limits and two lower limits alarms) ,the thermocouple breaking alarm, mutual isolative the 0~10 V direct-current analogue output and the CENTRONICS standard digital output, and the alarm relay contact output. These intelligent type sodium instrumentations are suitable particularly for the instrument, control and protective systems of LMFBR by means of these excel- lent functions based on microprocessor. The basic errors of the intelligent type sodi- um flowmeter, immersed sodium flowmeter, sodium manometer and sodium level gauge are ±2%, ±2- 3%, +0. 3% and +1- 9% of measuring range respectively.

E50. 00 JttffSI

WASTE MANAGEMENT

E51-00 Waste Treatment

CNIC-01113 960107

THE TECHNOLOGY,PROPOSE AND PROSPECT OF DISPOSAL WASTE WA- TER AT THE URANIUM MILLING PLANT/CHEN Shian (Beijing Research In- stitute of Chemical Engineering and Metallurgy) {In Chinese") The Precipitation method of neutralizing waste pulp and waste water with lime 87 milk i treatment of the tailings pond water by pyrolusite adsorption and air earation and barium chloride precipitation-precipitates of hydroxides to flocculate as carriers and technology feature, amenability and application for one comprehensive treat- ment of waste water and waste pulp before they release to tailing pond are de- scribed. Practice shows that using new technique and technology for processing ura- nium ores, using comprehensively resource, recovering useful materials, utilizating wastes for disposing wastes, cycling technological water, strengthening production management can perfect waste water disposal and treatment system which is short process, low cost and better effect, whereby can reach aim at both temporary solu- tion and permanent control.

F00. 00

OTHER ASPECTS OF NUCLEAR ENERGY

F10. 00 frfc£S

ECONOMICS AND SOCIOLOGY

FII. oo Wh-h&ft

Nuclear Power Economics

CNIC-01124 960108 BICM-0015

. n

r- «ik '& THE POSITION, ROLE AND DEVELOPMENT PROSPECTS OF NUCLEAR ENERGY IN CHINA ENERGY SYSTEM/ZHENG Yuhui YAN Jimin (China Institute of Nuclear Industry Economics, Beijing) The fundamental features of the present China's energy system are discussed and analyzed, and points out that since the founding of the People's Republic of China, although the energy construction, including the development and use of nu- clear energy, has achieved great success, the average energy resource per capita is still low. The following major issues, such as the transportation pressure raised from the energy structure of taking coal as the main, the increasing seriousness of envi- ronmental pollution, large amount of Greenhouse gases emission and low " energy efficiency" , etc. , have constrained the sustainable development of national economy and society. In accordance with the position of nuclear energy in the strategy of the energy development in south-east coastal areas of China, and the analysis of " value criteria" and "decision goal" system for the development and use of nuclear energy, it is described that the development of nuclear energy is an important way and the optimum selection to optimize China's energy system. In accordance with the fun- damental policy and technical line, and the technical ability and foundation condi- tions , the strategic target, scale and overall arrangement for the development of China's nuclear power are proposed and the bright future for the development of China's nuclear power industry is comprehensively discussed and analyzed.

F60. 00

MISCELLANEOUS

F61-00 -&±M General Relevant documents

CNIC-01050 960109 (1996^) / (*B&ffNs* fr

89 ABSTRACTS CHINA NUCLEAR SCIENCE &. TECHNOLOGY REPORT/ (1996) (China Nuclear Information Centre, Beijing) The bibliographies and abstracts of China Nuclear Science and Technology Re- ports published in 1996 (Report Numbers CNIC-01021 — CNIC-01131) are pre- sented. The items are arranged according to INIS subject categories, which mainly are physical sciences, chemistry, materials, earth sciences, life sciences, isotopes, isotope and radiation applications, engineering and technology, and other aspects of nuclear energy. The numbers on the left corners of the entries are report numbers, and on the right corners the serial numbers. A report number index is annexed.

CNIC-01112 940110 RINPO-0017

i-"in>t. n

SCHEDULING AND COORDINATION FOR IN-SERVICE INSPECTION OF NUCLEAR POWER PLANT/LI Songbai (Research Institute of Nuclear Power Operation, Wuhan) Based on the practice and experiences of pre-service and in-service inspections for Daya Bay Nuclear Power Plant (NPP) by Research Institute of Nuclear Power Operation (RINPO) following RSEM code, requirements of utility and actual situa- tion in China, the in-service inspection preparation for organization, techniques and equipment/tooling,materials,personnel and documentation is briefly described. And the scheduling and coordinating consideration for planed in-service inspection activi- ties during NPP outage is emphatically introduced.

90 Index

CNIC—01021 960056 CNIC—01054 960003 CNIC—01022 960061 CNIC—01055 960046 CNIC—01023 960065 CNIC—01056 960058 CNIC—01024 960028 CNIC—01057 960067 CNIC—01025 960062 CNIC—01058 960101 CNIC—01026 960004 CNIC—01059 960001 CNIC—01027 960042 CNIC—01060 960072 CNIC—01028 960017 CNIC—01061 960019 CNIC—01029 960084 CNIC—01062 960073 CNIC—01030 960013 CNIC—01063 960059 CNIC—01031 960089 CNIC—01064 960007 CNIC—01032 960018 CNIC—01065 960096 CNIC—01033 960040 CNIC—01066 960033 CNIC—01034 960005 CNIC—01067 960047 CNIC—01035 960068 CNIC—01068 960074 CNIC—01036 960094 CNIC—01069 960020 CNIC—01037 960031 CNIC—01070 960060 CNIC— 01038 960099 CNIC—01071 960021 CNIC—01039 960071 CNIC—01072 960106 CNIC—01040 960090 CNIC—01073 960034 CNIC—01041 960054 CNIC—01074 960035 CNIC—01042 960032 CNIC—01075 960014 CNIC—01043 960100 CNIC—01076 960075 CNIC—01044 960043 CNIC—01077 960022 CNIC—01045 960044 CNIC—01078 960076 CNIC—01046 960066 CNIC—01079 960069 CNIC—01047 960046 CNIC—01080 960015 CNIC—01048 960085 CNIC—01081 960091 CNIC—01049 960057 CNIC—01082 960008 CNIC—01050 960109 CNIC—01083 960016 CNIC—01051 960006 CNIC—01084 960029 CNIC—01052 960097 CNIC—01085 960048 CNIC—01053 960079 CNIC—01086 960030 91 CNIC -0108V 960041 CNIC—01109 960051 CNIC—01088 960063 CNIC—oino 960105 CNIC—01089 960049 CNIC—01111 960038 CNIC—01090 960009 CNIC—01112 960110 CNIC—01091 960064 CNIC—01113 960107 CNIC—01092 960081 CNIC—01114 960052 CNIC—01093 960010 CNIC—01115 960025 CNIC—01094 960088 CNIC—01116 960082 CNIC—01095 960102 CNIC—01117 960011 CNIC—01096 960070 CNIC—01118 960078 CNIC—01097 960023 CNIC—01119 960083 CNIC—01098 960024 CNIC—01120 960093 CNIC—01099 960103 CNIC—01121 960098 CNIC—01100 960055 CNIC—01122 960086 CNIC—01101 960077 CNIC—01123 9^0039 CNIC—01102 9^0036 CNIC—01124 960108 CNIC—01103 960095 CNIC—01125 960026 CNIC—01104 960050 CNIC—01126 960027 CNIC—01105 960092 CNIC—01127' 960080 CNIC—01106 960104 CNIC—01128 9<;oor>3 CNIC 01107 960002 CNIC—01129 960087 CNIC —01108 960037 CNIC- 01130 960012

92 a & *

^ jt £ 2103 jf ^| 10

100037o

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93 TL-2. CHINA NUCLEAR SCIENCE & TECHNOLOGY REPORT

This report is subject to copyright. All rights are reserved. Submission of a report for publication implies the transfer of the exclusive publication right from the author(s) to the publisher. No part of this publication,except abstract, may be reproduced, stored in data banks or transmitted in any form or by any means, electronic,mechanical,photocopying,recording or otherwise, without the prior written permission of the publisher, China Nuclear Information Centre, and/or Atomic Energy Press. Violations fall under the prosecution act of the Copyright Law of China. The China Nuclear Information Centre and Atomic Energy Press do not accept any responsibility for loss or damage arising from the use of information contained in any of its reports or in any communication about its test or investigations.

ISBN 7-5022-1773-8

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