Neutron Imaging: a Non-Destructive Tool for Materials Testing
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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 -
Neutron Activation System for Spectral Measurements of Pulsed Ion Diode Neutron Production
Q-,? \^ <A \ SAND79-2196 Unlimited Rtlciie UC-37 #^ Neutron Activation System for Spectral Measurements of Pulsed Ion Diode Neutron Production Dwid L. Hanton, Ly(# W. Kniw 1 I. Introduction The ability to characterize neutron energy spectra is essential for the application of intense pulsed neutron sources to radiation effects simulation and fusion materials damage studies. However, the problems of neutron detection are par ticularly severe in the environment of relativistic electron beam (REB) accelerators where intense electromagnetic and bremsstrahlung x-ray pulses are generated. A system for de tecting neutrons in such a harsh radiation environment has been developed for use with Sandia's pulsed accelerators and is described in a previous report. The essential components of this system are: (1) total neutron yield detectors (Ag activation 2 counters) to determine the total number of neutrons from a pulse; (2) a fast response time, high efficiency time-of- flight (TOF) spectrometer, consisting of a shielded liquid scintillator and gated photo- multiplier of special design, to characterize the time distribution and approximate energy spectrum of the neutrons; and (3) a neutron activation system to accurately de termine the neutron energy spectrum. This integrated diagnostic system is able to provide a complete picture of the time and energy di s*-ribution of neutrons produced in a REB diode shot. However, the neutron activation system of Ref. 1 made use a Nal(Tlj well crystal 5 to detect residual activity and was severely limited in its effectiveness by coincidence sum effects. The purpose of the present report is to describe the design of a much improved neutron activation system and its application as a neutron spectrometer in a recent series of Hermes II neutron produc tion experiments. -
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. -
Three Dimensional Polarimetric Neutron Tomography of Magnetic
www.nature.com/scientificreports OPEN Three Dimensional Polarimetric Neutron Tomography of Magnetic Fields Received: 25 April 2017 Morten Sales 1, Markus Strobl 2,3, Takenao Shinohara4, Anton Tremsin5, Luise Theil Kuhn 6, Accepted: 18 January 2018 William R. B. Lionheart7, Naeem M. Desai 7, Anders Bjorholm Dahl8 & Søren Schmidt 1 Published: xx xx xxxx Through the use of Time-of-Flight Three Dimensional Polarimetric Neutron Tomography (ToF 3DPNT) we have for the frst time successfully demonstrated a technique capable of measuring and reconstructing three dimensional magnetic feld strengths and directions unobtrusively and non- destructively with the potential to probe the interior of bulk samples which is not amenable otherwise. Using a pioneering polarimetric set-up for ToF neutron instrumentation in combination with a newly developed tailored reconstruction algorithm, the magnetic feld generated by a current carrying solenoid has been measured and reconstructed, thereby providing the proof-of-principle of a technique able to reveal hitherto unobtainable information on the magnetic felds in the bulk of materials and devices, due to a high degree of penetration into many materials, including metals, and the sensitivity of neutron polarisation to magnetic felds. The technique puts the potential of the ToF time structure of pulsed neutron sources to full use in order to optimise the recorded information quality and reduce measurement time. Te spin of a neutron passing through a magnetic feld will undergo an amount of precession proportional to the strength of the magnetic feld and the time spent by the neutron in the magnetic feld. Te time is proportional to the neutron wavelength, λ, and the path length through the magnetic feld, L. -
Neutron Activation and Prompt Gamma Intensity in Ar/CO $ {2} $-Filled Neutron Detectors at the European Spallation Source
Neutron activation and prompt gamma intensity in Ar/CO2-filled neutron detectors at the European Spallation Source E. Diana,b,c,∗, K. Kanakib, R. J. Hall-Wiltonb,d, P. Zagyvaia,c, Sz. Czifrusc aHungarian Academy of Sciences, Centre for Energy Research, 1525 Budapest 114., P.O. Box 49., Hungary bEuropean Spallation Source ESS ERIC, P.O Box 176, SE-221 00 Lund, Sweden cBudapest University of Technology and Economics, Institute of Nuclear Techniques, 1111 Budapest, M}uegyetem rakpart 9. dMid-Sweden University, SE-851 70 Sundsvall, Sweden Abstract Monte Carlo simulations using MCNP6.1 were performed to study the effect of neutron activation in Ar/CO2 neutron detector counting gas. A general MCNP model was built and validated with simple analytical calculations. Simulations and calculations agree that only the 40Ar activation can have a considerable effect. It was shown that neither the prompt gamma intensity from the 40Ar neutron capture nor the produced 41Ar activity have an impact in terms of gamma dose rate around the detector and background level. Keywords: ESS, neutron detector, B4C, neutron activation, 41Ar, MCNP, Monte Carlo simulation 1. Introduction Ar/CO2 is a widely applied detector counting gas, with long history in ra- diation detection. Nowadays, the application of Ar/CO2-filled detectors is ex- tended in the field of neutron detection as well. However, the exposure of arXiv:1701.08117v2 [physics.ins-det] 16 Jun 2017 Ar/CO2 counting gas to neutron radiation carries the risk of neutron activa- tion. Therefore, detailed consideration of the effect and amount of neutron ∗Corresponding author Email address: [email protected] (E. -
ICANS XXI Dawn of High Power Neutron Sources and Science Applications
Book of Abstracts ICANS XXI Dawn of high power neutron sources and science applications 29 Sep - 3 Oct 2014, JAPAN Ibaraki Prefectural Culture Center Update : 12 Oct. 2014 Best photography in 7th Oarai Town Photo Contest. WELCOME TO ICANS XXI ICANS (International Collaboration on Advanced Neutron Sources) is a network for scientists who are involved in developing pulsed neutron sources and accelerator based spallation neutron sources. Since 1st ICANS meetings was held in 1977 at Argonne National Laboratory in the day of dawn of spallation neutron technique, ICANS has been continuously held already 20 times somewhere in the world. Now we are extremely happy to announce that the ICANS, the 21st meeting, will be held at Mito hosted by J-PARC this autumn. We have a large number of topics to be discussed, there are twelve topics, such as futuristic idea of neutron source, rapid progress in facilities, integration issues in target-moderator-development, etc. The details can be found in the agenda. The meeting has a two layered structure, one is plenary session and another is workshop. Two of them are complementary and tightly cooperate each other. In the meeting we would like to enhance "workshop style", which is an original and traditional way of ICANS. Actually 2/3 of topics will be discussed in the workshop sessions. It also will be essentially organized/ lead by the workshop chairs. Plenary session shows overall issues in a relevant workshop, whose details should be talked/discussed in the workshop. The venue for the meeting is Mito city, where the 2nd Shogun Family lived for a long period of time during Edo era from 17th to 19th century, when the Tokugawa shogunate ruled the country. -
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. -
An Exploration of Neutron Detection in Semiconducting Boron Carbide
University of Nebraska - Lincoln DigitalCommons@University of Nebraska - Lincoln Theses, Dissertations, and Student Research: Department of Physics and Astronomy Physics and Astronomy, Department of 4-2012 An Exploration of Neutron Detection in Semiconducting Boron Carbide Nina Hong University of Nebraska-Lincoln, [email protected] Follow this and additional works at: https://digitalcommons.unl.edu/physicsdiss Part of the Physics Commons Hong, Nina, "An Exploration of Neutron Detection in Semiconducting Boron Carbide" (2012). Theses, Dissertations, and Student Research: Department of Physics and Astronomy. 20. https://digitalcommons.unl.edu/physicsdiss/20 This Article is brought to you for free and open access by the Physics and Astronomy, Department of at DigitalCommons@University of Nebraska - Lincoln. It has been accepted for inclusion in Theses, Dissertations, and Student Research: Department of Physics and Astronomy by an authorized administrator of DigitalCommons@University of Nebraska - Lincoln. An Exploration of Neutron Detection in Semiconducting Boron Carbide by Nina Hong A DISSERTATION Presented to the Faculty of The Graduate College of the University of Nebraska In Partial Fulfillment of Requirements For the Degree of Doctor of Philosophy Major: Physics & Astronomy Under the Supervision of Professor Shireen Adenwalla Lincoln, Nebraska April, 2012 An Exploration of Neutron Detection in Semiconducting Boron Carbide Nina Hong, Ph.D. University of Nebraska, 2012 Advisor: Shireen Adenwalla The 3He supply problem in the U.S. has necessitated the search for alternatives for neutron detection. The neutron detection efficiency is a function of density, atomic composition, neutron absorption cross section, and thickness of the neutron capture material. The isotope 10B is one of only a handful of isotopes with a high neutron absorption cross section—3840 barns for thermal neutrons. -
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. -
Application of 3D Neutron Imaging and Tomography in Cultural Heritage Research
F1-RC-1219.1 LIMITED DISTRIBUTION International Atomic Energy Agency Coordinated Research Project on Application of 3D Neutron Imaging and Tomography in Cultural Heritage Research Report of the first Research Co-ordination Meeting Vienna, Austria 07 - 11 May 2012 Reproduced by the IAEA Vienna, Austria, 2012 NOTE The material reproduced here has been supplied by the authors and has not been edited by the IAEA. The views expressed remain the responsibility of the named authors and do not necessarily reflect those of the government(s) of the designating Member State(s). In particular, neither the IAEA nor any other organization or body sponsoring the meeting can be held responsible for this material CONTENTS 1. FOREWORD .................................................................................................................... 1 2. EXECUTIVE SUMMARY ............................................................................................... 2 3. INTRODUCTION ............................................................................................................. 3 4. CRP OBJECTIVES ........................................................................................................... 4 4.1. Objectives of the CRP ............................................................................................ 4 4.2. Objectives of 1st RCM meeting ............................................................................. 4 4.3 Working groups: .................................................................................................... -
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.