Alternatives to MOX Direct-Disposal Options for Stockpiles of Separated Plutonium
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1, 2002, Sheraton Crystal City Hotel, Arlington, Virginia
Minutes for the Nuclear Energy Research Advisory Committee Meeting September 30 to October 1, 2002, Sheraton Crystal City Hotel, Arlington, Virginia NERAC members present: John Ahearne Dale Klein (Monday only) Thomas Cochran Robert Long Joseph Comfort Warren F. Miller, Jr. Michael Corradini Sekazi Mtingwa Jose Luis Cortez Richard Reba (Monday only) Maureen Crandall (Monday afternoon Joy Rempe and Tuesday only) Allen Sessoms Allen Croff Daniel Sullivan James Duderstadt (Chair) John Taylor Marvin Fertel (Monday only) Neil Todreas Beverly Hartline Joan Woodard (Monday only) Andrew Klein NERAC members absent: Steve Fetter Lura Powell Leslie Hartz C. Bruce Tarter J. Bennett Johnston Ashok Thadani (ad hoc) Linda C. Knight Charles E. Till Benjamin F. Montoya Also present: Ralph Bennett, Director for Advanced Nuclear Energy, Idaho National Engineering and Environmental Laboratory David Berg, Office of Environmental Management, DOE Nancy Carder, NERAC Staff Herbert Feinroth, President, Gamma Engineering Corp. John Gutteridge, University Programs, NE, USDOE Norton Haberman, Senior Technical Advisor, NE, USDOE Anthony Hechanova, Director, AAA University Participation Program, University of Nevada at Las Vegas R. Shane Johnson, Associate Director, Office of Technology and International Cooperation, NE, USDOE Silvia Jurisson, Department of Chemistry, University of Missouri, Columbia Owen Lowe, Associate Director, Office of Isotopes for Medicine and Science, NE, USDOE William Magwood, Director, NE, USDOE William Martin, Washington Policy Institute -
Ceramic Mineral Waste-Forms for Nuclear Waste Immobilization
materials Review Ceramic Mineral Waste-Forms for Nuclear Waste Immobilization Albina I. Orlova 1 and Michael I. Ojovan 2,3,* 1 Lobachevsky State University of Nizhny Novgorod, 23 Gagarina av., 603950 Nizhny Novgorod, Russian Federation 2 Department of Radiochemistry, Lomonosov Moscow State University, Moscow 119991, Russia 3 Imperial College London, South Kensington Campus, Exhibition Road, London SW7 2AZ, UK * Correspondence: [email protected] Received: 31 May 2019; Accepted: 12 August 2019; Published: 19 August 2019 Abstract: Crystalline ceramics are intensively investigated as effective materials in various nuclear energy applications, such as inert matrix and accident tolerant fuels and nuclear waste immobilization. This paper presents an analysis of the current status of work in this field of material sciences. We have considered inorganic materials characterized by different structures, including simple oxides with fluorite structure, complex oxides (pyrochlore, murataite, zirconolite, perovskite, hollandite, garnet, crichtonite, freudenbergite, and P-pollucite), simple silicates (zircon/thorite/coffinite, titanite (sphen), britholite), framework silicates (zeolite, pollucite, nepheline /leucite, sodalite, cancrinite, micas structures), phosphates (monazite, xenotime, apatite, kosnarite (NZP), langbeinite, thorium phosphate diphosphate, struvite, meta-ankoleite), and aluminates with a magnetoplumbite structure. These materials can contain in their composition various cations in different combinations and ratios: Li–Cs, Tl, Ag, Be–Ba, Pb, Mn, Co, Ni, Cu, Cd, B, Al, Fe, Ga, Sc, Cr, V, Sb, Nb, Ta, La, Ce, rare-earth elements (REEs), Si, Ti, Zr, Hf, Sn, Bi, Nb, Th, U, Np, Pu, Am and Cm. They can be prepared in the form of powders, including nano-powders, as well as in form of monolith (bulk) ceramics. -
Dissolution of Uranium Dioxide in Nitric Acid Media: What Do We Know?
EPJ Nuclear Sci. Technol. 3, 13 (2017) Nuclear © Sciences P. Marc et al., published by EDP Sciences, 2017 & Technologies DOI: 10.1051/epjn/2017005 Available online at: http://www.epj-n.org REGULAR ARTICLE Dissolution of uranium dioxide in nitric acid media: what do we know? Philippe Marc1, Alastair Magnaldo1,*, Aimé Vaudano1, Thibaud Delahaye2, and Éric Schaer3 1 CEA, Nuclear Energy Division, Research Department of Mining and Fuel Recycling Processes, Service of Dissolution and Separation Processes, Laboratory of Dissolution Studies, 30207 Bagnols-sur-Cèze, France 2 CEA, Nuclear Energy Division, Research Department of Mining and Fuel Recycling Processes, Service of Actinides Materials Fabrication, Laboratory of Actinide Conversion Processes, 30207 Bagnols-sur-Cèze, France 3 Laboratoire Réactions et Génie des Procédés, UMR CNRS 7274, University of Lorraine, 54001 Nancy, France Received: 16 March 2016 / Received in final form: 15 November 2016 / Accepted: 14 February 2017 Abstract. This article draws a state of knowledge of the dissolution of uranium dioxide in nitric acid media. The chemistry of the reaction is first investigated, and two reactions appear as most suitable to describe the mechanism, leading to the formation of monoxide and dioxide nitrogen as reaction by-products, while the oxidation mechanism is shown to happen before solubilization. The solid aspect of the reaction is also investigated: manufacturing conditions have an impact on dissolution kinetics, and the non-uniform attack at the surface of the solid results in the appearing of pits and cracks. Last, the existence of an autocatalytic mechanism is questionned. The second part of this article presents a compilation of the impacts of several physico-chemical parameters on the dissolution rates. -
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. -
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. -
Economic Development Board 1 South Australia
ECONOMIC DEVELOPMENT BOARD 1 SOUTH AUSTRALIA 3 August 2015 Rear Admiral the Honourable Kevin Sca rce AC CSC RAN (Rtd) Roya l Commissioner for the Nuclear Fuel Cycle Royal Commission Level 5, 50 Grenfell Street Adelaide SA 5000 Dear Commissioner RE: Nuclear fuel Cycle Royal Commission I write to provide a discussion paper prepared by ThinkCiimate for the Economic Development Board (EDB), that responds to the four issues papers released by the Nuclear Fuel Cycle Roya l Commission on: Exploration, Extraction and Milling; Further Processing and Manufacture; Electricity Generation; and Management, Storage and Disposal of Waste. In October 2014, in the absence of reliable and cu rrent data and evidence on the nuclear value chain, the EDB commissioned ThinkCiimate Consulting to prepare a discussion paper. The purpose of the discussion paper was to explore the opportunities for an expanded role for South Australia in the nuclear value chain and to provide a high level business case to indicate if there is sufficient economic potential to warrant a more thorough investigation. The discussion paper, provided to you as Attachment 1 to this letter, explores the economic opportunities for South Australia at each point in the nuclear value cha in and, therefore, responds to the four Issues Papers released. The discussion paper concludes that: • There is potentially a major economic opportunity for South Australia in the safe management of spent nuclear fuel based on merging mature Intermediate Spent Fuel Storage Installation (ISFI) technology with Generation IV recycling and reactor technology. • Further a preliminary project assessment finds that a proposed configuration of an ISFSI and Integrated Fast Reactor (IFR) technology would utilise up to approximately 99% of the stored fuel to generate electricity as a low-cost, emissions free baseload with potentially significant economic benefits to South Australia within a relatively short timeframe. -
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. -
A Review of the Nuclear Fuel Cycle Strategies and the Spent Nuclear Fuel Management Technologies
energies Review A Review of the Nuclear Fuel Cycle Strategies and the Spent Nuclear Fuel Management Technologies Laura Rodríguez-Penalonga * ID and B. Yolanda Moratilla Soria ID Cátedra Rafael Mariño de Nuevas Tecnologías Energéticas, Universidad Pontificia Comillas, 28015 Madrid, Spain; [email protected] * Correspondence: [email protected]; Tel.: +34-91-542-2800 (ext. 2481) Received: 19 June 2017; Accepted: 6 August 2017; Published: 21 August 2017 Abstract: Nuclear power has been questioned almost since its beginnings and one of the major issues concerning its social acceptability around the world is nuclear waste management. In recent years, these issues have led to a rise in public opposition in some countries and, thus, nuclear energy has been facing even more challenges. However, continuous efforts in R&D (research and development) are resulting in new spent nuclear fuel (SNF) management technologies that might be the pathway towards helping the environment and the sustainability of nuclear energy. Thus, reprocessing and recycling of SNF could be one of the key points to improve the social acceptability of nuclear energy. Therefore, the purpose of this paper is to review the state of the nuclear waste management technologies, its evolution through time and the future advanced techniques that are currently under research, in order to obtain a global vision of the nuclear fuel cycle strategies available, their advantages and disadvantages, and their expected evolution in the future. Keywords: nuclear energy; nuclear waste management; reprocessing; recycling 1. Introduction Nuclear energy is a mature technology that has been developing and improving since its beginnings in the 1940s. However, the fear of nuclear power has always existed and, for the last two decades, there has been a general discussion around the world about the future of nuclear power [1,2]. -
Progress Report
SYNROC STUDY GROUP PROGRESS REPORT August 1991 SYNROC STUDY PROGRESS REPORT August 1991 The Broken Hill Proprietary Company Limited (A.CN. 004 028 077) CRA Limited (A.C.N. 004 458 404) Energy Resources of Australia Limited (A.C.N. 008 550 865) Western Mining Corporation Limited (A.C.N. 004 184 598) Australian Nuclear Science and Technology Organisation Australian National University OVERVIEW This Progress Report has been prepared by the Synroc Study Group (SSG), comprising staff members of The Australian Nuclear Science and Technology Organisation (ANSTO), The Australian National University (ANU), BHP, CRA, Energy Resources of Australia (ERA) and Western Mining Corporation (WMC). It also draws upon work undertaken for the SSG by consultants from Nuclear Assurance Corporation (market estimates), the Swedish Nuclear Fuel and Waste Management Company (SKB) (cost estimates and other data) and Wave Hill Associates (US and international perspectives). Synroc is applicable solely to the immobilisation of liquid high-level waste after such waste has been separated from spent fuel in a reprocessing operation; use of Synroc therefore requires prior construction of a reprocessing plant An alternative management strategy, based upon direct disposal of encapsulated spent nuclear fuel, does not require reprocessing, and therefore makes no use of Synroc. The SSG has examined both of these alternatives and also a third, which is to defer decision-making on reprocessing versus direct disposal for a lengthy period while spent fuel is held in interim storage. The SSG recognises that many utilities and countries have deferred decisions as between reprocessing and direct disposal of spent fuel. The construction of interim spent fuel storage facilities and related infrastructure appears to be a practical strategy in the short term, although for many utilities and countries this period of satisfactory and acceptable deferral may be starting to run out. -
Letterhead World Nuclear Association
ISSUES PAPER 4 – MANAGEMENT, STORAGE, DISPOSAL OF NUCLEAR AND RADIOACTIVE WASTE Submission from the World Nuclear Association to the South Australian Nuclear Fuel Cycle Royal Commission Introduction The World Nuclear Association is grateful for this opportunity to answer the Commission’s questions regarding the management, storage and disposal of radioactive wastes in South Australia. There is considerable international experience in handling radioactive material and wastes, which it may be noted are neither particularly hazardous nor hard to manage relative to some other toxic industrial wastes. The storage and handling of civil nuclear wastes has been safely undertaken for more than 50 years. The aim in radioactive waste management is to protect people and the environment utilising three general principles – concentration and containment, dilution and dispersal, delay and decay. The first two principles are also used in the management of other, non-radioactive, wastes. The third principle works by storing the waste long enough until radioactive decay renders the waste no longer radiologically hazardous. Unlike some other toxic wastes, such as heavy metals, the principal hazard associated with nuclear waste – radioactivity – diminishes with time. The pillar of any national waste management plan is the responsible implementation of an institutional framework. Authoritative international organisations provide advice on institutional frameworks for the management of nuclear wastes. These include the International Atomic Energy Agency (IAEA), the Nuclear Energy Agency (NEA) of the Organisation for Economic Co-operation and Development (OECD), the European Commission (EC) and the International Commission on Radiological Protection (ICRP). International agreements in the form of conventions under the auspices of the IAEA have also been established, such as the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management.