The Bimodal Neutron and X-Ray Imaging Driven by a Single Electron Linear Accelerator
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Spent Nuclear Fuel Pools in the US
Spent Nuclear Fuel Pools in the U.S.: Reducing the Deadly Risks of Storage front cover WITH SUPPORT FROM: WITH SUPPORT FROM: By Robert Alvarez 1112 16th St. NW, Suite 600, Washington DC 20036 - www.ips-dc.org May 2011 About the Author Robert Alvarez, an Institute for Policy Studies senior scholar, served as a Senior Policy Advisor to the Secre- tary of Energy during the Clinton administration. Institute for Policy Studies (IPS-DC.org) is a community of public scholars and organizers linking peace, justice, and the environment in the U.S. and globally. We work with social movements to promote true democracy and challenge concentrated wealth, corporate influence, and military power. Project On Government Oversight (POGO.org) was founded in 1981 as an independent nonprofit that investigates and exposes corruption and other misconduct in order to achieve a more effective, accountable, open, and ethical federal government. Institute for Policy Studies 1112 16th St. NW, Suite 600 Washington, DC 20036 http://www.ips-dc.org © 2011 Institute for Policy Studies [email protected] For additional copies of this report, see www.ips-dc.org Table of Contents Summary ...............................................................................................................................1 Introduction ..........................................................................................................................4 Figure 1: Explosion Sequence at Reactor No. 3 ........................................................4 Figure 2: Reactor No. 3 -
MASTER 9700 South Cass Avenue Argonne, Illinois 60439 USA
ANL/KDH—SO DE84 001440 ANL/NDM-80 NEUTRON TOTAL CROSS SECTION MEASUREMENTS IN THE ENERGY REGION FROM 47 key to 20 MeV* by W. P. Poenitz and J. F. Whalon Applied Physics Division May, 1983 *This work supported by the U.S. Department of Energy Argonne National Laboratory MASTER 9700 South Cass Avenue Argonne, Illinois 60439 USA fflSTRtBtfUOU OF miS DOCUMENT IS UNLIMITED NUCLEAR DATA AMD MEASUREMENTS SERIES The Nuclear Data and Measurements Series presents results of studies in the field of microscopic nuclear data. The primary objective is the dissemination of information in the comprehensive form required for nuclear technology applications. This Series is devoted to: a) measured microscopic nuclear parameters, b) experimental techniques and facilities employed in measurements, c) the analysis, correlation and interpretation of nuclear data, and d) the evaluation of nuclear data. Contributions to this Series are reviewed to assure technical competence and, unless otherwise stated, the contents can be formally referenced. This Series does not supplant formal journal publication but it does provide the more extensive informa- tion required for technological applications (e.g., tabulated numerical data) in a timely manner. DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or retpoosi- bility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Refer- ence herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom- mendation, or favoring by the United States Government or any agency thereof. -
Progress in Fusion-Driven Transmutation Research in China
Progress in Fusion-Driven Transmutation Research in China Yican WU Institute of Plasma Physics, Chinese Academy of Sciences P.O. Box 1126, Hefei, Anhui, 230031, China E-mail: [email protected] Fax: +86 551 5591310 1. Introduction Although the recent experiments and associated theoretical studies of fusion energy development have proven the feasibility of fusion power, it's commonly realized that it needs hard work before pure fusion energy could commercially and economically utilized. On the other hand, the fission nuclear industry has been falling on hard times recently since so far there has been no conclusion about how to deal with the long-lived wastes produced from the nuclear spent fuel and about how to solve the shortage of natural uranium ore in addition to nuclear safety and proliferation. It's a natural way to develop fusion-fission hybrid reactors including fuel producing reactors and waste transmuting reactors as an alternate strategy to speed up the time for producing energy since a hybrid reactor as a subcritical system can operate with lower fusion energy gain ratios Q, therefore the design of the fusion core for a hybrid system is easier than for a pure fusion reactor. The fusion-fission hybrid concept dates back to the earliest days of the fusion project when it was recognized that using fusion neutrons to breed nuclear fuel would vastly increase the energy from fusion plant. It appears to receive almost no attention since the mid 80's in the world, except in China who has given very serious consideration and has strong hybrid reactor activities since 1986 in the framework of the National Hi’Tech Program supported by the State Science and Technology Commission (SSTC) of China. -
Uses of Isotopic Neutron Sources in Elemental Analysis Applications
EG0600081 3rd Conference on Nuclear & Particle Physics (NUPPAC 01) 20 - 24 Oct., 2001 Cairo, Egypt USES OF ISOTOPIC NEUTRON SOURCES IN ELEMENTAL ANALYSIS APPLICATIONS A. M. Hassan Department of Reactor Physics Reactors Division, Nuclear Research Centre, Atomic Energy Authority. Cairo-Egypt. ABSTRACT The extensive development and applications on the uses of isotopic neutron in the field of elemental analysis of complex samples are largely occurred within the past 30 years. Such sources are used extensively to measure instantaneously, simultaneously and nondestruclively, the major, minor and trace elements in different materials. The low residual activity, bulk sample analysis and high accuracy for short lived elements are improved. Also, the portable isotopic neutron sources, offer a wide range of industrial and field applications. In this talk, a review on the theoretical basis and design considerations of different facilities using several isotopic neutron sources for elemental analysis of different materials is given. INTRODUCTION In principle there are two ways to use neutrons for elemental and isotopic abundance analysis in samples. One is the neutron activation analysis which we call it the "off-line" where the neutron - induced radioactivity is observed after the end of irradiation. The other one we call it the "on-line" where the capture gamma-rays is observed during the neutron bombardment. Actually, the sequence of events occurring during the most common type of nuclear reaction used in this analysis namely the neutron capture or (n, gamma) reaction, is well known for the people working in this field. The neutron interacts with the target nucleus via a non-elastic collision, a compound nucleus forms in an excited state. -
PGNAA Neutron Source Moderation Setup Optimization
Submitted to ‘Chinese Physics C PGNAA neutron source moderation setup optimization Zhang Jinzhao1(张金钊)Tuo Xianguo1(庹先国) (1.Chengdu University of Technology Applied Nuclear Techniques in Geoscience Key Laboratory of Sichuan Province,Chengdu 610059,China) Abstract: Monte Carlo simulations were carried out to design a prompt γ-ray neutron activation analysis (PGNAA) thermal neutron output setup using MCNP5 computer code. In these simulations the moderator materials, reflective materials and structure of the PGNAA 252Cf neutrons of thermal neutron output setup were optimized. Results of the calcuations revealed that the thin layer paraffin and the thick layer of heavy water moderated effect is best for 252Cf neutrons spectrum. The new design compared with the conventional neutron source design, the thermal neutron flux and rate were increased by 3.02 times and 3.27 times. Results indicate that the use of this design should increase the neutron flux of prompt gamma-ray neutron activation analysis significantly. Key word: PGNAA; neutron source; thermal neutron; moderation; reflection 1. Introduction study, Monte Carlo calculation was carried out for the Prompt gamma ray neutron activation analysis design of a 252Cf neutron source moderation setup for the (PGNAA) is a rapid, nondestructive, powerful analysis cement samples[7]. The model of Monte Carlo multielemental analysis technique, large samples of some simulation was verified by experiment[8, 9].We improve minor, trace light elements and is used in industrial the thermal neutron source yield rate of 252Cf neutron by control[1-5]. In a PGNAA analysis, the sample nuclear the PGNAA neutron source structure to the design. The composition is determined from prompt gamma rays calculation results for the new design were compared which produced through neutron inelastic scattering and with the previous, example: themal neutron flux rate, fast thermal neutron capture. -
Arxiv:1506.05417V2 [Physics.Ins-Det] 28 Jul 2016
http://dx.doi.org/10.1016/j.apradiso.2016.06.032 A precise method to determine the activity of a weak neutron source using a germanium detector M. J. M. Dukea, A. L. Hallinb, C. B. Kraussb, P. Mekarskib,∗, L. Sibleyb aSLOWPOKE Nuclear Reactor Facility, University of Alberta, Edmonton, AB T6G 2G7, Canada bDepartment of Physics, University of Alberta, Edmonton, AB T6G 2E1, Canada Abstract A standard high purity germanium (HPGe) detector was used to determine the previously unknown neutron activity of a weak americium-beryllium (AmBe) neutron source. γ rays were created through 27Al(n,n0), 27Al(n,γ) and 1H(n,γ) reactions induced by the neutrons on aluminum and acrylic disks, respectively. These γ rays were measured using the HPGe detector. Given the unorthodox experimental arrangement, a Monte Carlo simulation was developed to model the efficiency of the detector system to determine the neutron activity from the measured γ rays. The activity of our neutron source was determined to be 307.4 ± 5.0 n/s and is consistent for the different neutron-induced γ rays. Keywords: neutron activation, germanium detector, simulation, spectroscopy, activity determination 1. Introduction As neutrons are difficult to detect, determining the absolute activity of a neutron source is challenging. This difficulty increases as the activity of the source decreases. Sophisticated techniques exist for neutron activity measure- ments, including the manganese bath technique[1], proton recoil techniques[2] and the use of 3He proportional counters[3]; nevertheless, the development of a method utilizing commonly available high purity germanium (HPGe) detectors would be advantageous. HPGe's are an industry standard for measuring γ ray energies to high preci- sion. -
A Novel Energy Resolved Neutron Imaging Detector Based On
A novel energy resolved neutron imaging detector based on TPX3Cam for the CSNS Jianqing Yang1,2,3, Jianrong Zhou2,3,4*, Xingfen Jiang2,3,4, Jinhao Tan2,3,5, Lianjun Zhang2,3,5, Jianjin Zhou2,3, Xiaojuan Zhou2,3,Wenqin Yang2,3,4,Yuanguang Xia2,3, Jie Chen2,3, XinLi Sun1, Quanhu Zhang1**, Zhijia Sun2,3,4***, Yuanbo Chen2,3,4 1. Xi’an Research Institute of Hi-Tech, 710025, Xian,China. 2. Spallation Neutron Source Science Center, Dongguan, 523803, Guangdong, China; 3. State Key Laboratory of Particle Detection and Electronics, Institute of High Energy Physics, Chinese Academy of Sciences, Beijing, 100049, China; 4. University of Chinese Academy of Sciences, Beijing 100049, China 5. Harbin Engineering University, Harbin, Heilongjiang, China, 150000 Abstract: The China Spallation Neutron Source (CSNS) operates in pulsed mode and has a high neutron flux. This provides opportunities for energy resolved neutron imaging by using the TOF (Time Of Flight) approach. An Energy resolved neutron imaging instrument (ERNI) is being built at the CSNS but significant challenges for the detector persist because it simultaneously requires a spatial resolution of less than 100 μm, as well as a microsecond-scale timing resolution. This study constructs a prototype of an energy resolved neutron imaging detector based on the fast optical camera, TPX3Cam coupled with an image intensifier. To evaluate its performance, a series of proof of principle experiments were performed in the BL20 at the CSNS to measure the spatial resolution and the neutron wavelength spectrum, and perform neutron imaging with sliced wavelengths and Bragg edge imaging of the steel sample. -
Nuclear Weapons Technology 101 for Policy Wonks Bruce T
NUCLEAR WEAPONS TECHNOLOGY FOR POLICY WONKS NUCLEAR WEAPONS TECHNOLOGY 101 FOR POLICY WONKS BRUCE T. GOODWIN BRUCE T. GOODWIN BRUCE T. Center for Global Security Research Lawrence Livermore National Laboratory August 2021 NUCLEAR WEAPONS TECHNOLOGY 101 FOR POLICY WONKS BRUCE T. GOODWIN Center for Global Security Research Lawrence Livermore National Laboratory August 2021 NUCLEAR WEAPONS TECHNOLOGY 101 FOR POLICY WONKS | 1 This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory in part under Contract W-7405-Eng-48 and in part under Contract DE-AC52-07NA27344. The views and opinions of the author expressed herein do not necessarily state or reflect those of the United States government or Lawrence Livermore National Security, LLC. ISBN-978-1-952565-11-3 LCCN-2021907474 LLNL-MI-823628 TID-61681 2 | BRUCE T. GOODWIN Table of Contents About the Author. 2 Introduction . .3 The Revolution in Physics That Led to the Bomb . 4 The Nuclear Arms Race Begins. 6 Fission and Fusion are "Natural" Processes . 7 The Basics of the Operation of Nuclear Explosives. 8 The Atom . .9 Isotopes . .9 Half-life . 10 Fission . 10 Chain Reaction . 11 Critical Mass . 11 Fusion . 14 Types of Nuclear Weapons . 16 Finally, How Nuclear Weapons Work . 19 Fission Explosives . 19 Fusion Explosives . 22 Staged Thermonuclear Explosives: the H-bomb . 23 The Modern, Miniature Hydrogen Bomb . 25 Intrinsically Safe Nuclear Weapons . 32 Underground Testing . 35 The End of Nuclear Testing and the Advent of Science-Based Stockpile Stewardship . 39 Stockpile Stewardship Today . 41 Appendix 1: The Nuclear Weapons Complex . -
Neutron Sources
Neutron Sources Nadia Fomin Fundamental Neutron Physics Summer School Knoxville, TN 2015 Much content “borrowed” from Kevin Anderson, Mike Snow, Geoff 1 Greene, Scott Dewey, Mike Moncko, Jack Carpenter, and many others http://knoxbeerweek.com/ Neutron Sources Nadia Fomin Fundamental Neutron Physics Summer School Knoxville, TN 2015 Much content “borrowed” from Kevin Anderson, Mike Snow, Geoff 3 Greene, Scott Dewey, Mike Moncko, Jack Carpenter, and many others What is neutron physics ? Research which uses “low energy” neutrons from nuclear reactors and accelerator-driven spallation sources to address questions in nuclear, particle, and astrophysics Neutron Properties -22 Electric charge: qn=0, electrically neutral [qn<10 e] -5 -25 2 Size: rn~10 Angstrom=1 Fermi [area~ 10 cm =0.1 “barn”] Internal Structure: quarks [ddu, md~ mu~few MeV ] + gluons Spin: sn= 1/2 [Fermi statistics] Magnetic Dipole Moment: mn/ mp = -0.68497935(17) -26 Electric Dipole Moment: zero[dn < 10 e-cm] Mass: mn=939.566 MeV [mn> mp+ me, neutrons can decay] Lifetime: tn=880ish (depends on whom you ask) Neutrons are hard to get Neutrons are bound in nuclei, need several MeV for liberation E E=0 We want E~kT~25 meV (room temperature) VNN How to slow down a heavy neutral particle with Mn= Mp ? Lots of collisions… p n [1/2]N=(1 MeV)/(25 meV) for N collisions E 0 E/2 Neutrons are unstable when free->they can’t be accumulated easily Neutrons: Fast and Furious. And slow and gentle . Thermal ~25meV (2200m/s, λT=1.8Å) . Cold 50μeV-25meV . Very cold 2x10-7 - 5x10-5 eV . -
Fundamentals of Nuclear Power
Fundamentals of Nuclear Power Juan S. Giraldo Douglas J. Gotham David G. Nderitu Paul V. Preckel Darla J. Mize State Utility Forecasting Group December 2012 Table of Contents List of Figures .................................................................................................................................. iii List of Tables ................................................................................................................................... iv Acronyms and Abbreviations ........................................................................................................... v Glossary ........................................................................................................................................... vi Foreword ........................................................................................................................................ vii 1. Overview ............................................................................................................................. 1 1.1 Current state of nuclear power generation in the U.S. ......................................... 1 1.2 Nuclear power around the world ........................................................................... 4 2. Nuclear Energy .................................................................................................................... 9 2.1 How nuclear power plants generate electricity ..................................................... 9 2.2 Radioactive decay ................................................................................................. -
Behaviour of Neutron Moderator Materials at High Temperatures in CASTOR®-Casks: Qualification and Assessment
14th International Symposium on the Packaging and Paper # 235 Transportation of Radioactive Materials (PATRAM 2004), Berlin, Germany, September 20-24, 2004 Behaviour of Neutron Moderator Materials at High Temperatures in CASTOR®-Casks: Qualification and Assessment Torsten Krietsch1), Dietmar Wolff1), Ulrich Knopp2) and Hans-Dieter Brocke3) 1) Federal Institute for Materials Research and Testing (BAM), Berlin, Germany 2) Gesellschaft für Nuklear-Behälter mbH (GNB), Essen, Germany 3) TÜV Rheinland Group, Berlin, Germany 1. Introduction The Federal Institute for Materials Research and Testing (BAM) is the responsible German authority for the assessment of mechanical and thermal designs of transport and storage casks for radioactive materials. BAM checks up the proofs of the applicants in their safety reports and assesses the conformity to the Regulations for the Safe Transport of Radioactive Material [1, 2]. One applicant is the Gesellschaft für Nuklear-Behälter mbH (GNB) with a new generation of transport and storage casks of CASTOR®-design. GNB typically uses ultra high molecular weight Polyethylene (UHMW-PE) for the moderation of free neutrons. Rods made of UHMW-PE are positioned in axial bore holes in the wall of the cask and plates of UHMW-PE are in free spaces between primary and secondary lid and between the bottom of the cask and an outer plate (Figure 1). Because of the heat generated by the radioactive inventory and because of a strained spring at the bottom of every bore hole, UHMW- PE is subjected to permanent thermal and mechanical loads as well as loads from gamma and neutron radiation. UHMW-PE has been used under routine- and normal conditions of transport for maximum temperatures up to 130 °C. -
Neutron Imaging- a Nondestructive Diagnostic Tool for Material Science
Presents: Muhammad Abir, Ph.D. Imaging Specialist Phoenix, LLC Neutron Imaging- A Nondestructive Diagnostic Tool for Material Science Abstract: Neutron imaging is a powerful non-invasive technique in various applications for probing the internal structure of much thicker objects as well as for imaging of low Z materials. Particularly in situations, where penetration through x-rays is difficult, neutron imaging plays an important role. Manufacturers of complex parts through additive manufacturing processes or large high-density items that may not be well suited to x-rays finds the benefits of neutron imaging intriguing. Manufacturers of composite materials, turbine blade manufacturers, and manufacturers utilizing investment casting techniques are also interested to see how neutron radiography can find residual ceramic core material leftover from chemical leaching and dissolving processes. Neutrons are generated either from a neutron generating isotope (e.g. UW Madison nuclear reactor) in a reactor facility or from a deuterium-deuterium or deuterium- tritium neutron generator (e.g. Phoenix) or proton accelerator (e.g. SNS at ORNL). Depending on neutron energies, different neutron imaging systems can be developed. Usually the high- resolution (less than 10 µm) neutron imaging systems are developed with cold neutrons while the medium-resolution (usually 10 µm- 200 µm) neutron imaging systems can be developed with thermal neutrons. For dense samples that are not easily penetrable, mm-range resolution neutron imaging systems can be developed using fast neutrons. With the combination of X-ray and neutron imaging, the fusion between X-ray and neutron imaging can provide more insight about the materials. This talk will discuss Dr.