No Barriers to Reactor-Grade Plutonium Use in Nuclear Weapons
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Neutron Interactions and Dosimetry Outline Introduction Tissue
Outline • Neutron dosimetry Neutron Interactions and – Thermal neutrons Dosimetry – Intermediate-energy neutrons – Fast neutrons Chapter 16 • Sources of neutrons • Mixed field dosimetry, paired dosimeters F.A. Attix, Introduction to Radiological • Rem meters Physics and Radiation Dosimetry Introduction Tissue composition • Consider neutron interactions with the majority tissue elements H, O, C, and N, and the resulting absorbed dose • Because of the short ranges of the secondary charged particles that are produced in such interactions, CPE is usually well approximated • Since no bremsstrahlung x-rays are generated, the • The ICRU composition for muscle has been assumed in absorbed dose can be assumed to be equal to the most cases for neutron-dose calculations, lumping the kerma at any point in neutron fields at least up to 1.1% of “other” minor elements together with oxygen to an energy E ~ 20 MeV make a simple four-element (H, O, C, N) composition Neutron kinetic energy Neutron kinetic energy • Neutron fields are divided into three • Thermal neutrons, by definition, have the most probable categories based on their kinetic energy: kinetic energy E=kT=0.025eV at T=20C – Thermal (E<0.5 eV) • Neutrons up to 0.5eV are considered “thermal” due to simplicity of experimental test after they emerge from – Intermediate-energy (0.5 eV<E<10 keV) moderator material – Fast (E>10 keV) • Cadmium ratio test: • Differ by their primary interactions in tissue – Gold foil can be activated through 197Au(n,)198Au interaction and resulting biological effects -
Table 2.Iii.1. Fissionable Isotopes1
FISSIONABLE ISOTOPES Charles P. Blair Last revised: 2012 “While several isotopes are theoretically fissionable, RANNSAD defines fissionable isotopes as either uranium-233 or 235; plutonium 238, 239, 240, 241, or 242, or Americium-241. See, Ackerman, Asal, Bale, Blair and Rethemeyer, Anatomizing Radiological and Nuclear Non-State Adversaries: Identifying the Adversary, p. 99-101, footnote #10, TABLE 2.III.1. FISSIONABLE ISOTOPES1 Isotope Availability Possible Fission Bare Critical Weapon-types mass2 Uranium-233 MEDIUM: DOE reportedly stores Gun-type or implosion-type 15 kg more than one metric ton of U- 233.3 Uranium-235 HIGH: As of 2007, 1700 metric Gun-type or implosion-type 50 kg tons of HEU existed globally, in both civilian and military stocks.4 Plutonium- HIGH: A separated global stock of Implosion 10 kg 238 plutonium, both civilian and military, of over 500 tons.5 Implosion 10 kg Plutonium- Produced in military and civilian 239 reactor fuels. Typically, reactor Plutonium- grade plutonium (RGP) consists Implosion 40 kg 240 of roughly 60 percent plutonium- Plutonium- 239, 25 percent plutonium-240, Implosion 10-13 kg nine percent plutonium-241, five 241 percent plutonium-242 and one Plutonium- percent plutonium-2386 (these Implosion 89 -100 kg 242 percentages are influenced by how long the fuel is irradiated in the reactor).7 1 This table is drawn, in part, from Charles P. Blair, “Jihadists and Nuclear Weapons,” in Gary A. Ackerman and Jeremy Tamsett, ed., Jihadists and Weapons of Mass Destruction: A Growing Threat (New York: Taylor and Francis, 2009), pp. 196-197. See also, David Albright N 2 “Bare critical mass” refers to the absence of an initiator or a reflector. -
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. -
TUTORIAL on NEUTRON PHYSICS in DOSIMETRY S. Pomp1
TUTORIAL ON NEUTRON PHYSICS IN DOSIMETRY S. Pomp1,* 1 Department of physics and astronomy, Uppsala University, Box 516, 751 20 Uppsala, Sweden. *Corresponding author. E‐mail address: [email protected] (S.Pomp) Abstract: Almost since the time of the discovery of the neutron more than 70 years ago, efforts have been made to understand the effects of neutron radiation on tissue and, eventually, to use neutrons for cancer treatment. In contrast to charged particle or photon radiations which directly lead to release of electrons, neutrons interact with the nucleus and induce emission of several different types of charged particles such as protons, alpha particles or heavier ions. Therefore, a fundamental understanding of the neutron‐nucleus interaction is necessary for dose calculations and treatment planning with the needed accuracy. We will discuss the concepts of dose and kerma, neutron‐nucleus interactions and have a brief look at nuclear data needs and experimental facilities and set‐ups where such data are measured. Keywords: Neutron physics; nuclear reactions; kerma coefficients; neutron beams; Introduction Dosimetry is concerned with the ability to determine the absorbed dose in matter and tissue resulting from exposure to directly and indirectly ionizing radiation. The absorbed dose is a measure of the energy deposited per unit mass in the medium by ionizing radiation and is measured in Gray, Gy, where 1 Gy = 1 J/kg. Radiobiology then uses information about dose to assess the risks and gains. A risk is increased probability to develop cancer due to exposure to a certain dose. A gain is exposure of a cancer tumour to a certain dose in order to cure it. -
Reference Values for Nuclear Criticality Safety
Nuclear Science ISBN 92-64-02333-X Reference Values for Nuclear Criticality Safety Homogeneous and Uniform UO2, “UNH”, PuO2 and “PuNH”, Moderated and Reflected by H2O A demonstration study by an Expert Group of the Working Party on Nuclear Criticality Safety for the OECD/NEA Nuclear Science Committee Final evaluation and report prepared by D. Mennerdahl (EMS, Sweden) Leading participants during the study W. Weber (GRS, Germany), Y. Naito (NAIS, Japan) and J. Anno (IRSN, France) Major organisations contributing with new calculation results EMS (Sweden), IPPE (Russia), IRSN (France), ORNL (US), Serco Ass. (UK) Reviewers of the final draft report include J.B. Briggs (INL), V. Rouyer (IRSN), S. Mitake (Japan), H. Okuno (Japan), Y. Rugama (OECD/NEA), R.M. Westfall (ORNL) © OECD 2006 NEA No. 5433 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT ORGANISATION FOR ECONOMIC COOPERATION AND DEVELOPMENT The OECD is a unique forum where the governments of 30 democracies work together to address the economic, social and environmental challenges of globalisation. The OECD is also at the forefront of efforts to understand and to help governments respond to new developments and concerns, such as corporate governance, the information economy and the challenges of an ageing population. The Organisation provides a setting where governments can compare policy experiences, seek answers to common problems, identify good practice and work to co-ordinate domestic and international policies. The OECD member countries are: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Korea, Luxembourg, Mexico, the Netherlands, New Zealand, Norway, Poland, Portugal, the Slovak Republic, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. -
Reactor Plutonium and Nuclear Explosives
Reactor Plutonium Utility in Nuclear Explosives* Bruce T. Goodwin, PhD Associate Director-at-Large for National Security & Policy Research *drawn from the work of Robert Selden November 6, 2015 LLNL-PRES-801535 This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under contract DE-AC52-07NA27344. Lawrence Livermore National Security, LLC Outline Bottom Line Up Front Plutonium Description Critical Mass Radioactivity & Heat Neutron Background A Nuclear Explosive Conclusions Summary Lawrence Livermore National Laboratory LL-NSO-U-2015-######_2 Bottom line up front • “A potential proliferating state or subnational group using designs and technologies no more sophisticated than those used in first-generation nuclear weapons could build a nuclear weapon from reactor grade plutonium that would have an assured, reliable yield of one or a few kilotons (and a probable yield significantly higher than that)” * • “An advanced nuclear weapon states such as the United States and Russia, using modern designs, could produce weapons from reactor grade plutonium having reliable explosive yields, weight, and other characteristics generally comparable to those of weapons made from weapons grade plutonium” * * Quoted from: US Department of Energy Publication “Nonproliferation and Arms Control Assessment of Weapons-Usable Fissile Material Storage and Excess Plutonium Disposition Alternatives, January 1997 http://www.osti.gov/scitech/biblio/425259 Lawrence Livermore National Laboratory LL-NSO-U-2015-######_3 -
Radiological Implications of Plutonium Recycle and the Use of Thorium Fuels in Power Reactor Operations
01 RD/B/N3523 Central Electricity Generating Board Research Department Berkeley Nuclear Laboratories RADIOLOGICAL IMPLICATIONS OF PLUTONIUM RECYCLE AND THE USE OF THORIUM FUELS IN POWER REACTOR OPERATIONS By H. F. Macdonald XJ034 January 1976 DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. Radiological Implications of Plutonium Recycle and the Use of Thorium Fuels in Power Reactor Operations “ by - H.F. Macdonald Approved Head of Health Physics Research Section For inclusion in Nuclear Science Abstracts SUMMARY As economically attractive sources of natural uranium are gradually depleted attention will turn to recycling plutonium or the use of thorium fuels. In this study the radiological implications of these fuel cycles in terms of fuel handling and radioactive waste disposal are investigated in 235 relation to a conventional U enriched oxide fuel. It is suggested that a comparative study of this nature may be an important aspect of the overall optimisation of future fuel cycle strategies. It is shown that the use of thorium based fuels has distinct advan tages in terms of neutron dose rates from irradiated fuels and long term a decay heating commitment compared with conventional uranium/plutonium fuels. However, this introduces a y dose rate problem in the fabrication 233 and handling of unirradiated U fuels. For both plutonium and thorium fuels these radiological problems increase during storage of the fuel prior to reactor irradiation. Finally, the novel health physics problems which arise in the handling and processing of thorium fuels are reviewed in an appendix. -
Conceptual Design Report Jülich High
General Allgemeines ual Design Report ual Design Report Concept Jülich High Brilliance Neutron Source Source Jülich High Brilliance Neutron 8 Conceptual Design Report Jülich High Brilliance Neutron Source (HBS) T. Brückel, T. Gutberlet (Eds.) J. Baggemann, S. Böhm, P. Doege, J. Fenske, M. Feygenson, A. Glavic, O. Holderer, S. Jaksch, M. Jentschel, S. Kleefisch, H. Kleines, J. Li, K. Lieutenant,P . Mastinu, E. Mauerhofer, O. Meusel, S. Pasini, H. Podlech, M. Rimmler, U. Rücker, T. Schrader, W. Schweika, M. Strobl, E. Vezhlev, J. Voigt, P. Zakalek, O. Zimmer Allgemeines / General Allgemeines / General Band / Volume 8 Band / Volume 8 ISBN 978-3-95806-501-7 ISBN 978-3-95806-501-7 T. Brückel, T. Gutberlet (Eds.) Gutberlet T. Brückel, T. Jülich High Brilliance Neutron Source (HBS) 1 100 mA proton ion source 2 70 MeV linear accelerator 5 3 Proton beam multiplexer system 5 4 Individual neutron target stations 4 5 Various instruments in the experimental halls 3 5 4 2 1 5 5 5 5 4 3 5 4 5 5 Schriften des Forschungszentrums Jülich Reihe Allgemeines / General Band / Volume 8 CONTENT I. Executive summary 7 II. Foreword 11 III. Rationale 13 1. Neutron provision 13 1.1 Reactor based fission neutron sources 14 1.2 Spallation neutron sources 15 1.3 Accelerator driven neutron sources 15 2. Neutron landscape 16 3. Baseline design 18 3.1 Comparison to existing sources 19 IV. Science case 21 1. Chemistry 24 2. Geoscience 25 3. Environment 26 4. Engineering 27 5. Information and quantum technologies 28 6. Nanotechnology 29 7. Energy technology 30 8. -
Properties of Selected Radioisotopes
CASE FILE COPY NASA SP-7031 Properties of Selected Radioisotopes A Bibliography PART I: UNCLASSIFIED LITERATURE NATIONAL AERONAUTICS AND SPACE ADMINISTRATION NASA SP-7031 PROPERTIES OF SELECTED RADIOISOTOPES A Bibliography Part I: Unclassified Literature A selection of annotated references to technical papers, journal articles, and books This bibliography was compiled and edited by DALE HARRIS and JOSEPH EPSTEIN Goddard Space Flight Center Greenbelt, Maryland Scientific and Technical Information Division / OFFICE OF TECHNOLOGY UTILIZATION 1968 USP. NATIONAL AERONAUTICS AND SPACE ADMINISTRATION Washington, D.C. PREFACE The increasing interest in the application of substantial quantities of radioisotopes for propulsion, energy conversion, and various other thermal concepts emphasizes a need for the most recent and most accurate information available describing the nuclear, chemical, and physical properties of these isotopes. A substantial amount of progress has been achieved in recent years in refining old and developing new techniques of measurement of the properties quoted, and isotope processing. This has resulted in a broad technological base from which both the material and information about the material is available. Un- fortunately, it has also resulted in a multiplicity of sources so that information and data are either untimely or present properties without adequately identifying the measurement techniques or describing the quality of material used. The purpose of this document is to make available, in a single reference, an annotated bibliography and sets of properties for nine of the more attractive isotopes available for use in power production. Part I contains all the unclassified information that was available in the literature surveyed. Part II is the classified counterpart to Part I. -
Sonie Applications of Fast Neutron Activation Analysis of Oxygen
S E03000182 CTH-RF- 16-5 Sonie Applications of Fast Neutron Activation Analysis of Oxygen Farshid Owrang )52 Akadenmisk uppsats roir avliiggande~ av ilosofie ficentiatexamen i Reaktorf'ysik vid Chalmer's tekniska hiigskola Examinator: Prof. Imre PiAst Handledare: Dr. Anders Nordlund Granskare: Bitr. prof. G~iran Nyrnan Department of Reactor Physics Chalmers University of Technology G6teborg 2003 ISSN 0281-9775 SOME APPLICATIONS OF FAST NEUTRON ACTIVATION OF OXYGE~'N F~arshid Owrang Chalmers University of Technology Departmlent of Reactor Physics SEP-1-412 96 G~iteborg ABSTRACT In this thesis we focus on applications of neutron activation of oxygen for several purposes: A) measuring the water level in a laboratory tank, B) measuring the water flow in a pipe system set-up, C) analysing the oxygen in combustion products formed in a modern gasoline S engine, and D) measuring on-line the amount of oxygen in bulk liquids. A) Water level measurements. The purpose of this work was to perform radiation based water level measurements, aimed at nuclear reactor vessels, on a laboratory scale. A laboratory water tank was irradiated by fast neutrons from a neutron enerator. The water was activated at different water levels and the water level was decreased. The produced gamma radiation was measured using two detectors at different heights. The results showed that the method is suitable for measurement of water level and that a relatively small experimental set-up can be used for developing methods for water level measurements in real boiling water reactors based on activated oxygen in the water. B) Water flows in pipe. -
Critical Mass Reduction
LA-3651 . ULL- a 4’ LOS ALAMOS SCIENTIFIC LABORATORY of the University of California LOS ALAMOS ● NEW MEXICO 1 k-——Critical Mass Reduction p.I 1--”— P- _—. I FORREFERENCE NOT TO BE TAKEN FROM THIS ROOM u,”mnv Wnuu CAT. NO. 1935 _ _— P ,-J UNITED STATES ATOMIC ENERGY COMMISSION CONTRACT W-7405 -ENG. 36 — s -., * LEGAL NOTICE This reportwas preparedas an accountof (governmentsponsoredwork. Neitherthe United States,northeCommhmion, nor any personactingon bebalfoftbeCommission: A. Makes any warrantyorrepresentation,expressedor implied,withrespecttotheaccu- racy,completeness,or usefulnessoftheinformationcontainedintbtsreport,or thattheuse of any information,apparatus,method,or processdtsclosedin tldsreportmay not infringe privatelyowned rights;or B. Assumes any liabilitieswttbrespecttotheuse of,or fordamages resultingfrom the useofany information,apparatus,method,or processdtsclosedinthisreport. As used in tbe above,“personacttngon bebalfof the Commission” includesany em- ployeeor contractorof theCommission,or employeeof such contractor,tothe extentthat such employeeor contractorof tbeCommission,or employeeof such contractorprepares, disseminates,or providesaccessto,any information~suant toMS employmentor contract withtheCommission,or bisemploymentwithsuchcontractor. This report expresses the opinionsof the author or authorsand does not necessarilyreflectthe opinions or views of the Los Alamos ScientificLaboratory. Printed in the United States of America. Available from Clearinghousefor Federal Scientificand TechnicalInformation NationalBureau of Standards,U. S. Department of Commerce Springfield,Virginia 22151 .Price: Printed Copy $ 3.00; Microfiche $0.65 .. -. LA-3651 UC-80, REACTOR TECHNOLOGY TID-4500 LOS ALAMOS SCIENTIFIC LABORATORY of the University of California LOS ALAMOS ● NEW MEXICO Report written: December 1, 1966 Report distributed:March 22, 1967 Critical Mass Reduction — -q by George A. Jarvis Carroll B. Mills ‘. .- -1- .. -. ABSTRACT A new low value for the critical mass of 23% in a critical. -
Practical Aspects of Operating a Neutron Activation Analysis Laboratory
IAEA-TECDOC-564 PRACTICAL ASPECTS OF OPERATING A NEUTRON ACTIVATION ANALYSIS LABORATORY A TECHNICAL DOCUMENT ISSUED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1990 PRACTICAL ASPECT OPERATINF SO G A NEUTRON ACTIVATION ANALYSIS LABORATORY IAEA, VIENNA, 1990 IAEA-TECDOC-564 ISSN 1011-4289 Printe IAEe th AustriAn i y d b a July 1990 PLEASE BE AWARE THAT MISSINE TH AL F LO G PAGE THIN SI S DOCUMENT WERE ORIGINALLY BLANK FOREWORD This boo s intendei k o advist d n everydai e y practical problems relateo t d operating a neutron activation analysis (NAA) laboratory. It gives answers to questions like "what to use NAA for", "how to find relevant research problems", "how to find users for the technique", "how to estimate the cost of the analysis and how to finance the work", "how to organize the work in a rational way d "ho"an o perforwt e qualitth m y control" givet I . s advice in choosing staff, equipment d consumableo desigt an , w nho facilitied an s s and procedures accordin neeo d availablt g an d e resources. e boo Th s designei k o discust d s problem t dealno s t wit n ordinari h A NA y textbooks, but also, in order to prevent it from being too voluminous, to avoid duplication of material described in normal NAA text books. Therefore e readeth , r will find that some materia f intereso l missins i t g from this book and it is recommended that one or two of the textbooks listed in chapter 11 be read in addition to this one.