NPR81: South Korea's Shifting and Controversial Interest in Spent Fuel
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When Sukarno Sought the Bomb: Indonesian Nuclear Aspirations in the Mid-1960S
ROBERT M. CORNEJO When Sukarno Sought the Bomb: Indonesian Nuclear Aspirations in the Mid-1960s ROBERT M. CORNEJO1 Robert M. Cornejo is a major in the US Army and a graduate of the United States Military Academy, West Point, New York. He recently earned an M.A. in National Security Affairs from the Naval Postgraduate School, Monterey, California, and is currently a student at the Singapore Command and Staff College. lthough Indonesia’s aspirations have been Sukarno’s successor, General Suharto, agreed to inter- largely forgotten today, in the mid-1960s, it national safeguards, thereby effectively ending concerns Asought to acquire and test nuclear weapons. In- that Indonesia might go nuclear. donesian government officials began publicizing their The purpose of this article is to tell the story of intent to acquire an atom bomb shortly after the People’s Indonesia’s nuclear aspirations, study Sukarno’s deci- Republic of China (PRC) exploded its first nuclear de- sion to support nuclear weapons, and identify variables vice in October 1964. By July 1965, Indonesian Presi- that may explain why he professed to seek the bomb. dent Sukarno was publicly vaunting his country’s future The article opens by tracing the evolution of Indonesia’s nuclear status. However, Indonesia did not have the in- nuclear aspirations, from a US Atoms for Peace pro- digenous capability necessary to produce its own nuclear gram of nuclear assistance that began in 1960, to weapon, and as a result, it would have had to secure Sukarno’s declared intention to acquire an atom bomb assistance from an established nuclear weapon state to in 1965. -
SAFETY RE-ASSESSMENT of AECL TEST and RESEARCH REACTORS D. J. WINFIELD Chalk River Nuclear Laboratories ATOMIC ENERGY of CANADA
309 IAEA-SM-310/ 94 SAFETY RE-ASSESSMENT OF AECL TEST AND RESEARCH REACTORS D. J. WINFIELD Chalk River Nuclear Laboratories ATOMIC ENERGY OF CANADA LIMITED 310 IAEA-SM-310/94 SAFETY RE-ASSESSMENT OF AECL TEST AND RESEARCH REACTORS ABSTRACT Atomic Energy of Canada Limited currently has four operating engineering test/research reactors of various sizes and ages; a new isotope-production reactor MAPLE-X10, under construction at Chalk River Nuclear Laboratories (CRNL), and a heating demonstration/test reactor, SDR, undergoing high-power commissioning at Whiteshell Nuclear Research Establishment (WNRE). The company is also performing design studies of small reactors for hot water and electricity production. The older reactors are ZED-2, PTR, NRX and NRU; these range in age from 42 years (NRX) to 29 years (ZED-2). Since 1984, limited-scope safety re-assessments have been underway on three of these reactors (ZED-2, NRX and NRU). ZED-2 and PTR are operated by the Reactor Physics Branch, all other reactors are operated by the respective site Reactor Operations Branches. For the older reactors the original safety reports produced were entirely deterministic in nature and based on the design-basis accident concept. The limited scope safety re-assessments for these older reactors, carried out over the past 5 years, have comprised both quantitative probabilistic safety-assessment techniques, such as event tree and fault tree analysis, and/or qualitative techniques, such as failure mode and effect analysis. The technique used for an individual assessment was dependent upon the specific scope required. This paper discusses the types of analyses carried out, specific insights/recommendations resulting from the analysis and indicates the plan for future analysis. -
Heu Repatriation Project
HEU REPATRIATION PROJECT RATIONALE In April 2010, the governments of Canada and the United States (U.S.) committed to work cooperatively to repatriate spent highly- enriched uranium (HEU) fuel currently stored at the Chalk River Laboratories in Ontario to the U.S. as part of the Global Threat Reduction Initiative, a broad international effort to consolidate HEU inventories in fewer locations around the world. This initiative PROJECT BACKGROUND promotes non-proliferation This HEU is the result of two decades of nuclear fuel use at the by removing existing weapons Chalk River Laboratories for Canadian Nuclear Laboratories (CNL) grade material from Canada research reactors, the National Research Experimental (NRX) and and transferring it to the National Research Universal (NRU), and for the production of U.S., which has the capability medical isotopes in the NRU, which has benefitted generations of to reprocess it for peaceful Canadians. Returning this material to the U.S. in its existing solid purposes. In March 2012, and liquid forms ensures that this material is stored safely in a Prime Minister Harper secure highly guarded location, or is reprocessed into other forms announced that Canada and that can be used for peaceful purposes. the U.S. were expanding their efforts to return additional Alternative approaches have been carefully considered and inventories of HEU materials, repatriation provides the safest, most secure, and fastest solution including those in liquid form. for the permanent disposition of these materials, thereby eliminating a liability for future generations of Canadians. For more information on this project contact: Email: [email protected] Canadian Nuclear Laboratories 1-866-886-2325 or visit: www.cnl.ca persons who have a legitimate need to PROJECT GOAL know, such as police or emergency response To repatriate highly-enriched uranium forces. -
Fuel Cycle Flexibility in CANDU P.G
IAEA-SM-353-5P Fuel Cycle Flexibility in CANDU P.G. Boczar XA9949933 Director, Fuel and Fuel Cycle Division, AECL Chalk River Laboratories, Chalk River, Ontario, Canada No single fuel-cycle path is appropriate for all countries. Many local and global factors will affect the best strategy for an individual country. Fuel-cycle flexibility is an important factor in an ever-changing, and unpredictable world. CANDU is an evolutionary reactor, offering a custom fuel cycle to fit local requirements. Its unsurpassed fuel-cycle flexibility can accommodate the widest range of fuel-cycle options in existing CANDU stations. In the short term, the CANFLEX® bundle is nearing power reactor implementation. The demonstration irradiation of 26 bundles in the Pt. Lepreau power station in New Brunswick, Canada, started this September, and a water-CHF test will take place later this year that will confirm the improvement in thermalhydraulic performance. CANFLEX provides enhanced operating and safety performance through a reduction in peak linear element ratings, and a significant increase in critical channel power. CANFLEX will be the near-term carrier of advanced fuel cycles. While natural uranium fuel provides outstanding advantages, the use of slightly enriched uranium (SEU) in CANDU offers even lower fuel cycle costs and other potential benefits, such as uprating capability through flattening the radial channel power distribution. Recycled uranium (RU) from reprocessing spent PWR fuel is a subset of SEU that has significant economic promise. The use of SEU/RU is the first logical step from natural uranium in CANDU. For countries having LWR reactors, the ability to use low-fissile material in CANDU reactors offers a range of unique synergistic fuel cycle opportunities. -
Tailings and Their Component Radionuclides from the Biosphere-Some Earth Science Perspectives
Tailings and Their Component Radionuclides From the Biosphere-Some Earth Science Perspectives Isolation of Uranium Mill Tailings and Their Component Radionuclides From the Biosphere-Some Earth Science Perspectives By Edward Landa GEOLOGICAL SURVEY CIRCULAR 814 A critical review of the literature dealing with uranium mill tailings, with emphasis on the geologic and geochemical processes affecting the long-term containment of radionuclides 1980 United States Department of the Interior CECIL D. ANDRUS, Secretary Geological Survey H. William Menard, Director Library of Congress catalog-card No. 79-600148 Free on application to Branch of Distribution, U.S. Geological Survey 1200 South Eads Street, Arlington, VA 22202 CONTENTS Page Abstract 1 Introduction ------------------------------------------------------------ 1 Acknowledginents ---------_----------------------------------------------- 2 Quantity and location of the tailings -------------------------------------- 2 Radioactivity in tailings -------------------------------------------------- 4 Sources of potential human radiation exposure from uranium mill tailings ------ 6 Radon emanation ----------------------------------------------------- 6 VVind transport ------------------------------------------------------- 6 Surface water transport and leaching ----------------------------------- 7 External gamma radiation ------------------------------------------- 8 Contamination of terrestrial and aquatic vegetation ---------------------- 8 Seepage ----------------------------------------------------~-------- -
Experience in Renovation of the Dalat Nuclear
THE CURRENT STATUS OF DALAT NUCLEAR RESEARCH REACTOR AND PROPOSED CORE CONVERSION STUDIES Pham Van Lam, Le Vinh Vinh, Huynh Ton Nghiem, Luong Ba Vien and Nguyen Kien Cuong Nuclear Research Institute 01 Nguyen Tu Luc St., Dalat, Vietnam Presented at the 24th International Meeting on Reduced Enrichment for Research and Test Reactors November 3-8, 2002 San Carlos de Bariloche, Argentina ABSTRACT: The Dalat Nuclear Research Reactor (DNRR) with nominal power of 500 kW accumulated eighteen years of operation in March 2002 since its renovation from the previous 250 kW TRIGA-MARK II reactor. It totaled 22703 hrs at nominal power. The total energy released was 473 MWd. The DNRR uses WWR-SM fuel assembly with 36% enrichment. Weight of uranium 235 in assembly is about 40.2 g. In April 1994, after more than 10 years of operation with 89 fuel assemblies, the first fuel reloading was executed. The 11 new fuel assemblies were added in the core periphery, at previous beryllium element locations. After reloading the working configuration of reactor core consisted of 100 fuel assemblies. The reloading operation increased the reactor excess reactivity from 3.8 $ to 6.5 $. This ensured exploitation of the DNRR for 8 years with 1200-1300 hrs per year at nominal power before second refueling. The second fuel reloading was executed in March 2002. The 4 new fuel assemblies were added in the core periphery, at previous beryllium element locations. After reloading the working configuration of reactor core consisted of 104 fuel assemblies. The reloading operation increased the reactor excess reactivity from 2.7 $ to 3.8 $. -
A Comprehensive Approach to Elimination of Highly-Enriched
Science and Global Security, 12:137–164, 2004 Copyright C Taylor & Francis Inc. ISSN: 0892-9882 print DOI: 10.1080/08929880490518045 AComprehensive Approach to Elimination of Highly-Enriched-Uranium From All Nuclear-Reactor Fuel Cycles Frank von Hippel “I would be prepared to submit to the Congress of the United States, and with every expectation of approval, [a] plan that would ... encourage world-wide investigation into the most effective peacetime uses of fissionable material...with the certainty that the investigators had all the material needed for the conducting of all experiments that were appropriate.” –President Dwight D. Eisenhower at the United Nations, Dec. 8, 1953, Over a period of about a decade after President Eisenhower’s “Atoms for Peace” speech, the U.S. and Soviet Union exported research reactors to about 40 countries. By the mid-1970s, most of these reactors were fueled with weapon-useable highly-enriched uranium (HEU), and most of those with weapon-grade uranium. In 1978, because of heightened concern about nuclear proliferation, both countries launched programs to develop low-enriched uranium (LEU) replacement fuel containing less than 20 percent 235U for foreign research reactors that they were supplying with HEU fuel. By the time the Soviet Union collapsed, most of the Soviet-supplied research reactors outside the USSR had been converted to 36% enriched uranium but the program then stalled because of lack of funding. By the end of 2003, the U.S. program had converted 31 reactors to LEU, including 11 within the U.S. If the development of very high density LEU fuel is successful, it appears that conversion of virtually all remaining research Received 12 January 2004; accepted 23 February 2004. -
THE NEXT GENERATION CANDU 6 J.M. HOPWOOD XA0053559 Atomic Energy of Canada Ltd, Mississauga, Ontario, Canada
IAEA-SM-353/29 THE NEXT GENERATION CANDU 6 illinium J.M. HOPWOOD XA0053559 Atomic Energy of Canada Ltd, Mississauga, Ontario, Canada Abstract AECL's product line of CANDU 6 and CANDU 9 nuclear power plants are adapted to respond to chang- ing market conditions, experience feedback and technological development by a continuous improvement process of design evolution. The CANDU 6 Nuclear Power Plant design is a successful family of nuclear units, with the first four units entering service in 1983, and the most recent entering service this year. A further four CANDU 6 units are under construction. Starting in 1996, a focused forward-looking development program is under way at AECL to incorporate a series of individual improvements and integrate them into the CANDU 6, leading to the evolutionary development of the next-generation enhanced CANDU 6. The CANDU 6 improvements program includes all aspects of an NPP project, including engineering tools improvements, design for improved constructability, scheduling for faster, more streamlined commissioning, and improved operating performance. This enhanced CANDU 6 product will combine the benefits of design provenness (drawing on the more than 70 reactor-years experience of the seven operating CANDU 6 units), with the advantages of an evolutionary next- generation design. Features of the enhanced CANDU 6 design include: • Advanced Human Machine Interface - built around the Advanced CANDU Control Centre. • Advanced fuel design - using the newly demonstrated CANFLEX fuel bundle. • Improved Efficiency based on improved utilization of waste heat. • Streamlined System Design - including simplifications to improve performance and safety system reliability. • Advanced Engineering Tools, - featuring linked electronic databases from 3D CADDS, equipment specifi- cation and material management. -
National Neutron Strategy-Draft
DRAFT FOR CONSULTATION A National Strategy for Materials Research with Neutron Beams: Discussion on a “National Neutron Strategy” This consultation draft was updated in February 2021, following the outcomes of the Canadian Neutron Initiative Roundtable: Towards a National Neutron Strategy, organized in partnership with CIFAR on December 15–16, 2020. 1 DRAFT FOR CONSULTATION This Canadian Neutron Initiative (CNI) discussion paper and associated Roundtable Meeting are produced in partnership with CIFAR. We also thank the following sponsors: 2 DRAFT FOR CONSULTATION Contents 1 Executive summary and overview of the national neutron strategy ................................................... 5 2 Consultation on the strategy ................................................................................................................ 9 3 The present: A strong foundation for continued excellence .............................................................. 10 3.1 The Canadian neutron beam user community ........................................................................... 10 3.2 McMaster University ................................................................................................................... 14 3.3 Other neutron beam capabilities and interests .......................................................................... 15 4 Forging foreign partnerships ............................................................................................................... 17 4.1 Global renewal of advanced neutron sources ........................................................................... -
Inventory of Radioactive Waste in Canada 2016 Inventory of Radioactive Waste in Canada 2016 Ix X 1.0 INVENTORY of RADIOACTIVE WASTE in CANADA OVERVIEW
Inventory of RADIOACTIVE WASTE in CANADA 2016 Inventory of RADIOACTIVE WASTE in CANADA 2016 Photograph contributors: Cameco Corp.: page ix OPG: page 34 Orano Canada: page x Cameco Corp.: page 47 BWX Technologies, Inc.: page 2 Cameco Corp.: page 48 OPG: page 14 OPG: page 50 OPG: page 23 Cameco Corp.: page 53 OPG: page 24 Cameco Corp.: page 54 BWX Technologies, Inc.: page 33 Cameco Corp.: page 62 For information regarding reproduction rights, contact Natural Resources Canada at [email protected]. Aussi disponible en français sous le titre : Inventaire des déchets radioactifs au Canada 2016. © Her Majesty the Queen in Right of Canada, as represented by the Minister of Natural Resources, 2018 Cat. No. M134-48/2016E-PDF (Online) ISBN 978-0-660-26339-7 CONTENTS 1.0 INVENTORY OF RADIOACTIVE WASTE IN CANADA OVERVIEW ���������������������������������������������������������������������������������������������� 1 1�1 Radioactive waste definitions and categories �������������������������������������������������������������������������������������������������������������������������������������������������� 3 1�1�1 Processes that generate radioactive waste in canada ����������������������������� 3 1�1�2 Disused radioactive sealed sources ����������������������������������������� 6 1�2 Responsibility for radioactive waste �������������������������������������������������������������������������������������������������������������������������������������������������������������������������� 6 1�2�1 Regulation of radioactive -
EMD Uranium (Nuclear Minerals) Committee
EMD Uranium (Nuclear Minerals) Committee EMD Uranium (Nuclear Minerals) Mid-Year Committee Report Michael D. Campbell, P.G., P.H., Chair December 12, 2011 Vice-Chairs: Robert Odell, P.G., (Vice-Chair: Industry), Consultant, Casper, WY Steven N. Sibray, P.G., (Vice-Chair: University), University of Nebraska, Lincoln, NE Robert W. Gregory, P.G., (Vice-Chair: Government), Wyoming State Geological Survey, Laramie, WY Advisory Committee: Henry M. Wise, P.G., Eagle-SWS, La Porte, TX Bruce Handley, P.G., Environmental & Mining Consultant, Houston, TX James Conca, Ph.D., P.G., Director, Carlsbad Research Center, New Mexico State U., Carlsbad, NM Fares M Howari, Ph.D., University of Texas of the Permian Basin, Odessa, TX Hal Moore, Moore Petroleum Corporation, Norman, OK Douglas C. Peters, P.G., Consultant, Golden, CO Arthur R. Renfro, P.G., Senior Geological Consultant, Cheyenne, WY Karl S. Osvald, P.G., Senior Geologist, U.S. BLM, Casper WY Jerry Spetseris, P.G., Consultant, Austin, TX Committee Activities During the past 6 months, the Uranium Committee continued to monitor the expansion of the nuclear power industry and associated uranium exploration and development in the U.S. and overseas. New power-plant construction has begun and the country is returning to full confidence in nuclear power as the Fukushima incident is placed in perspective. India, Africa and South America have recently emerged as serious exploration targets with numerous projects offering considerable merit in terms of size, grade, and mineability. During the period, the Chairman traveled to Columbus, Ohio to make a presentation to members of the Ohio Geological Society on the status of the uranium and nuclear industry in general (More). -
Radiation Safety Information Computational Center
Radiation Safety Information Computational Center Oak Ridge National Laboratory POST OFFICE BOX 2008 OAK RIDGE, TENNESSEE 37831-6362 Managed by UT-Battelle, LLC for the U.S. Department of Energy under contract DE-AC05-00OR22725 Phone No. 865-574-6176 FAX 865-574-6182 Internet: [email protected] http://www-rsicc.ornl.gov/rsic.html No. 448 June 2002 "The measure of a man's real character is what he would do if he knew he never would be found out." -- Thomas B. Macaulay Printable PDF file of this newsletter available at: http://www-rsicc.ornl.gov/NEWSLETTER.html. Azmy Elected as Fellow to ANS Congratulations to Dr. Yousry Azmy, ORNL, for being elected to Fellow Membership of the American Nuclear Society. The ANS is recognizing Dr. Azmy's contributions to the advancement of nuclear science and technology through the years. Dr. Azmy is a member of the Radiation Protection and Shielding Division and Mathematics and Computation Division. He will be honored at the Awards Luncheon June 11, in Hollywood, Florida. NOTICE RSICC will be offering a few data, processing, and computational tools free of handling, testing, and other fees associated with package transmittal. A ***NO FEE*** label will appear next to the package name on the web request page. The ability to provide these packages at no charge is due in part to advanced funding from the sponsors. To acquire these tools, follow the normal registration procedure for first-time or updated users. Then complete the WWW Request Form. The license and export control statements will need the user signatures, which is standard procedure.