Disposition of Fissile Material from Nuclear Weapons
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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. -
Combating Illicit Trafficking in Nuclear and Other Radioactive Material Radioactive Other Traffickingand Illicit Nuclear Combating in 6 No
8.8 mm IAEA Nuclear Security Series No. 6 Technical Guidance Reference Manual IAEA Nuclear Security Series No. 6 in Combating Nuclear Illicit and Trafficking other Radioactive Material Combating Illicit Trafficking in Nuclear and other Radioactive Material This publication is intended for individuals and organizations that may be called upon to deal with the detection of and response to criminal or unauthorized acts involving nuclear or other radioactive material. It will also be useful for legislators, law enforcement agencies, government officials, technical experts, lawyers, diplomats and users of nuclear technology. In addition, the manual emphasizes the international initiatives for improving the security of nuclear and other radioactive material, and considers a variety of elements that are recognized as being essential for dealing with incidents of criminal or unauthorized acts involving such material. Jointly sponsored by the EUROPOL WCO INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA ISBN 978–92–0–109807–8 ISSN 1816–9317 07-45231_P1309_CovI+IV.indd 1 2008-01-16 16:03:26 COMBATING ILLICIT TRAFFICKING IN NUCLEAR AND OTHER RADIOACTIVE MATERIAL REFERENCE MANUAL The Agency’s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. Its principal objective is “to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world’’. IAEA NUCLEAR SECURITY SERIES No. 6 TECHNICAL GUIDANCE COMBATING ILLICIT TRAFFICKING IN NUCLEAR AND OTHER RADIOACTIVE MATERIAL REFERENCE MANUAL JOINTLY SPONSORED BY THE EUROPEAN POLICE OFFICE, INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL POLICE ORGANIZATION, AND WORLD CUSTOMS ORGANIZATION INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 2007 COPYRIGHT NOTICE All IAEA scientific and technical publications are protected by the terms of the Universal Copyright Convention as adopted in 1952 (Berne) and as revised in 1972 (Paris). -
A Fissile Material Cut-Off Treaty N I T E D Understanding the Critical Issues N A
U N I D I R A F i s s i l e M a A mandate to negotiate a treaty banning the production of fissile material t e r i for nuclear weapons has been under discussion in the Conference of a l Disarmament (CD) in Geneva since 1994. On 29 May 2009 the Conference C u on Disarmament agreed a mandate to begin those negotiations. Shortly t - o afterwards, UNIDIR, with the support of the Government of Switzerland, f f T launched a project to support this process. r e a t This publication is a compilation of various products of the project, y : that hopefully will help to illuminate the critical issues that will need to U n be addressed in the negotiation of a treaty that stands to make a vital d e r contribution to the cause of nuclear disarmament and non-proliferation. s t a n d i n g t h e C r i t i c a l I s s u e s UNITED NATIONS INSTITUTE FOR DISARMAMENT RESEARCH U A Fissile Material Cut-off Treaty N I T E D Understanding the Critical Issues N A Designed and printed by the Publishing Service, United Nations, Geneva T I GE.10-00850 – April 2010 – 2,400 O N UNIDIR/2010/4 S UNIDIR/2010/4 A Fissile Material Cut-off Treaty Understanding the Critical Issues UNIDIR United Nations Institute for Disarmament Research Geneva, Switzerland New York and Geneva, 2010 Cover image courtesy of the Offi ce of Environmental Management, US Department of Energy. -
A New Methodology for Determining Fissile Mass in Individual Accounting Items with the Use of Gamma-Ray Spectrometry*
BNL-67176 A NEW METHODOLOGY FOR DETERMINING FISSILE MASS IN INDIVIDUAL ACCOUNTING ITEMS WITH THE USE OF GAMMA-RAY SPECTROMETRY* Walter R. Kane, Peter E. Vanier, Peter B. Zuhoski, and James R. Lemley Brookhaven National Laboratory Building 197C, P. O. Box 5000, Upton, NY 11973-5000 USA 631/344-3841 FAX 631/344-7533 Abstract In the safeguards, arms control, and nonproliferation regimes measurements are required which give the quantity of fissile material in an accounting item, e.g., a standard container of plutonium or uranium oxide. Because of the complexity of modeling the absorption of gamma rays in high-Z materials, gamma-ray spectrometry is not customarily used for this purpose. Gamma-ray measurements can be used to determine the fissile mass when two conditions are met: 1. The material is in a standard container, and 2. The material is finely divided, or a solid item with a reproducible shape. The methodology consists of: A. Measurement of the emitted gamma rays, and B. Measurement of the transmission through the item of the high-energy gamma rays of Co-60 and Th-228. We have demonstrated that items containing nuclear materials possess a characteristic "fingerprint" of gamma rays which depends not only on the nuclear properties, but also on the mass, density, shape, etc.. The material's spectrum confirms its integrity, homogeneity, and volume as well. While there is attenuation of radiation from the interior, the residual radiation confirms the homogeneity of the material throughout the volume. Transmission measurements, where the attenuation depends almost entirely on Compton scattering, determine the material mass. -
Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options
Order Code RL34579 Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options July 11, 2008 Mark Holt Specialist in Energy Policy Resources, Science, and Industry Division Advanced Nuclear Power and Fuel Cycle Technologies: Outlook and Policy Options Summary Current U.S. nuclear energy policy focuses on the near-term construction of improved versions of existing nuclear power plants. All of today’s U.S. nuclear plants are light water reactors (LWRs), which are cooled by ordinary water. Under current policy, the highly radioactive spent nuclear fuel from LWRs is to be permanently disposed of in a deep underground repository. The Bush Administration is also promoting an aggressive U.S. effort to move beyond LWR technology into advanced reactors and fuel cycles. Specifically, the Global Nuclear Energy Partnership (GNEP), under the Department of Energy (DOE) is developing advanced reprocessing (or recycling) technologies to extract plutonium and uranium from spent nuclear fuel, as well as an advanced reactor that could fully destroy long-lived radioactive isotopes. DOE’s Generation IV Nuclear Energy Systems Initiative is developing other advanced reactor technologies that could be safer than LWRs and produce high-temperature heat to make hydrogen. DOE’s advanced nuclear technology programs date back to the early years of the Atomic Energy Commission in the 1940s and 1950s. In particular, it was widely believed that breeder reactors — designed to produce maximum amounts of plutonium from natural uranium — would be necessary for providing sufficient fuel for a large commercial nuclear power industry. Early research was also conducted on a wide variety of other power reactor concepts, some of which are still under active consideration. -
MOX Fuel Program: Current Plans and Controversy
MOX Fuel Program: Current Plans and Controversy The Mixed Oxide (MOX) Fuel Fabrication Facility at Savannah River, South Carolina is intended to manufacture nuclear fuel from surplus weapons-grade plutonium for use in commercial nuclear energy reactors. However, the project has faced serious delays and massive cost overruns – and currently has no customers for its proposed fuel. As a result, the President’s FY17 Budget Proposal requests $270 million to begin closing the project, while diluting the plutonium for transfer to the Waste Isolation Pilot Plant (WIPP) in New Mexico, a more cost-efficient option. What Is It? The MOX facility at Savannah River was designed to repurpose 3.5 tonnes of surplus weapons-grade plutonium yearly. This facility was intended to play a key role in the United States’ fulfillment of the 2000 Plutonium Management and Disposition Agreement (PMDA) between Russia and the U.S., which affirms each country’s commitment to dispose of 34 metric tonnes of plutonium, enough collectively for 17,000 nuclear weapons. Challenges: The MOX Fuel Fabrication Facility’s anticipated date of operation was 2007, with plutonium disposition set to end in 2020. Multiple delays in construction led to significant cost overruns, with beginning operations delayed until 2019. Initially valued at $2.898 billion (2016 dollars), the total cost of the project skyrocketed to $15.683 billion as a result of construction delays and program mismanagement. This estimate, however, assumes a steady rate of funding, and fluctuations in funding levels could exacerbate delays and cost overruns. Even if completed, the site currently boasts zero customers for MOX fuel. -
Global Fissile Material Report 2006 a Table of Contents
IPF M Global Fis sile Material Report Developing the technical basis for policy initiatives to secure and irreversibly reduce stocks of nuclear weapons and fissile materials 2006 Over the past six decades, our understanding of the nuclear danger has expanded from the threat posed by the vast nuclear arsenals created by the super- powers in the Cold War to encompass the prolifera- tion of nuclear weapons to additional states and now also to terrorist groups. To reduce this danger, it is essential to secure and to sharply reduce all stocks of highly enriched uranium and separated plutonium, the key materials in nuclear weapons, and to limit any further production. The mission of the IPFM is to advance the technical basis for cooperative international policy initiatives to achieve these goals. A report published by Global Fissile The International Panel on Fissile Materials (IPFM) www.fissilematerials.org Program on Science and Global Security Princeton University Material Report 2006 221 Nassau Street, 2nd Floor Princeton, NJ 08542, USA First report of the International Panel on Fissile Materials First report of the International Panel on Fissile Materials Developing the Technical Basis for Policy Initiatives to Secure and Irreversibly Reduce Stocks of Nuclear Weapons and Fissile Materials www.fissilematerials.org Global Fissile Material Report 2006 a Table of Contents About the IPFM 1 Summary 2 I. Background 5 1 Fissile Materials and Nuclear Weapons 6 2 Nuclear-Weapon and Fissile-Material Stocks 12 3 Production and Disposition of Fissile -
Management of Reprocessed Uranium Current Status and Future Prospects
IAEA-TECDOC-1529 Management of Reprocessed Uranium Current Status and Future Prospects February 2007 IAEA-TECDOC-1529 Management of Reprocessed Uranium Current Status and Future Prospects February 2007 The originating Section of this publication in the IAEA was: Nuclear Fuel Cycle and Materials Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria MANAGEMENT OF REPROCESSED URANIUM IAEA, VIENNA, 2007 IAEA-TECDOC-1529 ISBN 92–0–114506–3 ISSN 1011–4289 © IAEA, 2007 Printed by the IAEA in Austria February 2007 FOREWORD The International Atomic Energy Agency is giving continuous attention to the collection, analysis and exchange of information on issues of back-end of the nuclear fuel cycle, an important part of the nuclear fuel cycle. Reprocessing of spent fuel arising from nuclear power production is one of the strategies for the back end of the fuel cycle. As a major fraction of spent fuel is made up of uranium, chemical reprocessing of spent fuel would leave behind large quantities of separated uranium which is designated as reprocessed uranium (RepU). Reprocessing of spent fuel could form a crucial part of future fuel cycle methodologies, which currently aim to separate and recover plutonium and minor actinides. The use of reprocessed uranium (RepU) and plutonium reduces the overall environmental impact of the entire fuel cycle. Environmental considerations will be important in determining the future growth of nuclear energy. It should be emphasized that the recycling of fissile materials not only reduces the toxicity and volumes of waste from the back end of the fuel cycle; it also reduces requirements for fresh milling and mill tailings. -
Appendix B Differences Between Thermal and Radiation Properties of Mixed Oxide and Low-Enriched Uranium Radioactive Materials
APPENDIX B DIFFERENCES BETWEEN THERMAL AND RADIATION PROPERTIES OF MIXED OXIDE AND LOW-ENRICHED URANIUM RADIOACTIVE MATERIALS The contents considered in this Standard Review Plan (SRP) appendix are unirradiated mixed oxide (MOX) radioactive material (RAM), in the form of powder, pellets, fresh fuel rods, or fresh reactor fuel assemblies. Unirradiated MOX RAM will also be referred to in this appendix as MOX fresh fuel. This appendix summarizes the relative degree of differences between the thermal and radiation properties of the various MOX RAM contents relative to similar properties for analogous low-enriched uranium (LEU) RAM contents. MOX fresh fuel can be made with plutonium having various compositions of plutonium isotopes. The discussion in this appendix makes use of the 3013 Standard (DOE 2012), which specifies the typical grades of plutonium that are used to make the MOX fresh fuel. The actual plutonium compositions found in practice may not match these compositions exactly, but these grades can be considered typical for the purposes of this appendix. Table B–6 of the 3013 Standard gives weight percents for various plutonium isotopes in various grades of plutonium. They are reproduced in the following table (Table B–1) as representative values for typical grades of plutonium that might be used to fabricate MOX fresh fuel. Pure plutonium-239 has been included to contrast the effect of the other plutonium isotopes. Note that in addition to the isotopes identified in Table B–1, plutonium will contain plutonium-236 and americium-241 (from plutonium-241 decay). Initially, it is expected that MOX fresh fuel will be fabricated using weapons grade (WG) plutonium. -
12Vac5-481 Virginia Radiation Protection Regulations
12VAC5-481 VIRGINIA RADIATION PROTECTION REGULATIONS PART I GENERAL PROVISIONS Section 10 Definitions Section 20 Scope Section 30 Deliberate misconduct Section 40 Reserved Section 50 Reserved Section 60 Reserved Section 70 Reserved Section 80 Reserved Section 90 Exemptions from regulatory requirements Section 100 Records Section 110 Inspections and enforcement Section 120 [Reserved] Section 130 Impounding Section 140 Prohibited uses Section 150 Communications Section 160 Effective date Section 170 Removal of notices posted by agency prohibited Section 180 Tests Section 190 Additional regulatory requirements Section 200 [Repealed] Section 210 Types of hearings Section 220 Hearing as a matter of right Section 230 Appeal Section 240 Units of exposure and dose Section 250 Units of radioactivity PART II REGISTRATION OF RADIATION MACHINE FACILITIES AND SERVICES Section 260 Purpose and scope Section 270 Exemptions Section 280 Shielding plan review Section 290 Registration of radiation machine facilities Section 300 Issuance of registration certificate Section 310 Renewal of registration and approval not implied Section 320 Expiration of registration certificate Section 330 Report of changes Section 340 Private inspector qualifications Section 350 Assembler or transfer obligation Section 360 Reciprocal recognition of out-of-state radiation machines Section 370 Certification of X-ray systems PART III LICENSING OF RADIOACTIVE MATERIAL Section 380 Purpose and scope Section 390 Source material Section 400 Radioactive material other than source material -
Highly Enriched Uranium: Striking a Balance
OFFICIAL USE ONLY - DRAFT GLOSSARY OF TERMS APPENDIX F GLOSSARY OF TERMS Accountability: That part of the safeguards and security program that encompasses the measurement and inventory verification systems, records, and reports to account for nuclear materials. Assay: Measurement that establishes the total quantity of the isotope of an element and the total quantity of that element. Atom: The basic component of all matter. Atoms are the smallest part of an element that have all of the chemical properties of that element. Atoms consist of a nucleus of protons and neutrons surrounded by electrons. Atomic energy: All forms of energy released in the course of nuclear fission or nuclear transformation. Atomic weapon: Any device utilizing atomic energy, exclusive of the means for transportation or propelling the device (where such means is a separable and divisible part of the device), the principal purpose of which is for use as, or for development of, a weapon, a weapon prototype, or a weapon test device. Blending: The intentional mixing of two different assays of the same material in order to achieve a desired third assay. Book inventory: The quantity of nuclear material present at a given time as reflected by accounting records. Burnup: A measure of consumption of fissionable material in reactor fuel. Burnup can be expressed as (a) the percentage of fissionable atoms that have undergone fission or capture, or (b) the amount of energy produced per unit weight of fuel in the reactor. Chain reaction: A self-sustaining series of nuclear fission reactions. Neutrons produced by fission cause more fission. Chain reactions are essential to the functioning of nuclear reactors and weapons. -
Framatome ANP MOX Fuel Design
BAW-10238(NP) Revision 0 43-10238NP-00 MOX Fuel Design Report March 2002 Framatome ANP, Inc. U.S. Nuclear Regulatory Commission Report Disclaimer Important Notice Regarding the Contents and Use of This Document Please Read Carefully This technical report was derived through research and development programs sponsored by Framatome ANP, Inc. It is being submitted by Framatome ANP, Inc. to the U.S. Nuclear Regulatory Commission as part of a technical contribution to facilitate safety analyses by licensees of the U.S. Nuclear Regulatory Commission which utilize Framatome ANP, Inc. fabricated reload fuel or technical services provided by Framatome ANP, Inc. for light water power reactors and it is true and correct to the best of Framatome ANP, Inc.'s knowledge, information, and belief. The information contained herein may be used by the U.S. Nuclear Regulatory Commission in its review of this report and, under the terms of the respective agreements, by licensees or applicants before the U.S. Nuclear Regulatory Commission which are customers of Framatome ANP, Inc. in their demonstration of compliance with the U.S. Nuclear Regulatory Commission's regulations. Framatome ANP, Inc.'s warranties and representations concerning the subject matter of this document are those set forth in the agreement between Framatome ANP, Inc. and the Customer pursuant to which this document is issued. Accordingly, except as otherwise expressly provided in such agreement, neither Framatome ANP, Inc. nor any person acting on its behalf: a. makes any warranty, or representation, express or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this document, or that the use of any information, apparatus, method, or process disclosed in this document will not infringe privately owned rights; or b.