The Slowpoke Licensing Model
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CHAPTER 13 Reactor Safety Design and Safety Analysis Prepared by Dr
1 CHAPTER 13 Reactor Safety Design and Safety Analysis prepared by Dr. Victor G. Snell Summary: The chapter covers safety design and safety analysis of nuclear reactors. Topics include concepts of risk, probability tools and techniques, safety criteria, design basis accidents, risk assessment, safety analysis, safety-system design, general safety policy and principles, and future trends. It makes heavy use of case studies of actual accidents both in the text and in the exercises. Table of Contents 1 Introduction ............................................................................................................................ 6 1.1 Overview ............................................................................................................................. 6 1.2 Learning Outcomes............................................................................................................. 8 1.3 Risk ...................................................................................................................................... 8 1.4 Hazards from a Nuclear Power Plant ................................................................................ 10 1.5 Types of Radiation in a Nuclear Power Plant.................................................................... 12 1.6 Effects of Radiation ........................................................................................................... 12 1.7 Sources of Radiation ........................................................................................................ -
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. -
CMD19-H100-8.Pdf
CMD 19-H100.8 File/dossier : 6.01.07 Date : 2019-08-30 Edocs pdf : 5983279 Oral Presentation Exposé oral Submission from Nuclear Waste Mémoire d’Action Déchets Nucléaires et Watch and Inter-Church Uranium Inter-Church Uranium Committee Committee Educational Cooperative Educational Cooperative In the Matter of À l’égard de Saskatchewan Research Council, Saskatchewan Research Council SLOWPOKE-2 Reactor Installation nucléaire SLOWPOKE-2 Request by the Saskatchewan Research Demande du Saskatchewan Research Council Council to authorize the decommissioning of afin d’autoriser le déclassement du réacteur the SLOWPOKE-2 reactor SLOWPOKE-2 Commission Public Hearing Audience publique de la Commission September 26, 2019 Le 26 septembre 2019 This page was intentionally Cette page a été intentionnellement left blank laissée en blanc Decommissioning of Saskatchewan Research Council SLOWPOKE-2 Reactor (Ref. 2019-H-100) Nuclear Waste Watch and Inter-Church Uranium Committee Educational Cooperative’s Submission to the Canadian Nuclear Safety Commission Prepared by: Jessica Karban Legal Counsel, Canadian Environmental Law Association August 30, 2019 ISBN: 978-1-77189-996-3 Publication No. 1290 Report from NWW & ICUCEC | 2 SUMMARY OF RECOMMENDATIONS Recommendation 1: In order to facilitate public participation, all Commission Member Documents (CMDs) and accompanying references should be made available on the CNSC’s website at least 60 days in advance of intervention deadlines and remain on the website for future public use. Recommendation 2: Based on our review of applicable requirements governing decommissioning in Canada, we request that the CNSC: 1. Develop a principled overall policy framework underpinning a robust, clear, and enforceable regulatory regime for the decommissioning of nuclear facilities as well as the waste that arises from nuclear and decommissioning activities; 2. -
NPR81: South Korea's Shifting and Controversial Interest in Spent Fuel
JUNGMIN KANG & H.A. FEIVESON Viewpoint South Korea’s Shifting and Controversial Interest in Spent Fuel Reprocessing JUNGMIN KANG & H.A. FEIVESON1 Dr. Jungmin Kang was a Visiting Research Fellow at the Center for Energy and Environmental Studies (CEES), Princeton University in 1999-2000. He is the author of forthcoming articles in Science & Global Security and Journal of Nuclear Science and Technology. Dr. H.A. Feiveson is a Senior Research Scientist at CEES and a Co- director of Princeton’s research Program on Nuclear Policy Alternatives. He is the Editor of Science and Global Security, editor and co-author of The Nuclear Turning Point: A Blueprint for Deep Cuts and De-alerting of Nuclear Weapons (Brookings Institution, 1999), and co-author of Ending the Threat of Nuclear Attack (Stanford University Center for International Security and Arms Control, 1997). rom the beginning of its nuclear power program could reduce dependence on imported uranium. During in the 1970s, the Republic of Korea (South Ko- the 1990s, the South Korean government remained con- Frea) has been intermittently interested in the cerned about energy security but also began to see re- reprocessing of nuclear-power spent fuel. Such repro- processing as a way to address South Korea’s spent fuel cessing would typically separate the spent fuel into three disposal problem. Throughout this entire period, the constituent components: the unfissioned uranium re- United States consistently and effectively opposed all maining in the spent fuel, the plutonium produced dur- reprocessing initiatives on nonproliferation grounds. We ing reactor operation, and the highly radioactive fission review South Korea’s evolving interest in spent fuel re- products and transuranics other than plutonium. -
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. -
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 -
Signatures of Weapon-Grade Plutonium from Dedicated Production Reactors Alexander Glaser Program on Science and Global Security, Princeton University
Signatures of Weapon-grade Plutonium from Dedicated Production Reactors Alexander Glaser Program on Science and Global Security, Princeton University 49th INMM Annual Meeting, Nashville, TN July 16, 2008 Revision 4 available at http://cstsp.aaas.org A. Glaser, Signatures of Weapon-grade Plutonium from Dedicated Production Reactors, 49th INMM Annual Meeting, July 13-17, 2008, Nashville, TN Overview Scope and Objective Quantify the range of isotopic variations that can be expected for plutonium produced with different types of dedicated production reactors Understand the relative importance of predictive versus empirical (isotopic) plutonium signatures (relevant, in particular, for nuclear forensic analysis) Methodology Neutronics calculations for several important production reactor types Using continuous-energy (MCNP) cross-section libraries to generate spectrum-averaged one-group cross-sections for burnup calculations and to assure that differences between results are not due to inconsistent cross-section data A. Glaser, Signatures of Weapon-grade Plutonium from Dedicated Production Reactors, 49th INMM Annual Meeting, July 13-17, 2008, Nashville, TN Isotope Ratio Correlations K. Mayer, M. Wallenius, and I. Ray, “Nuclear Forensics — A Methodology Providing Clues on the Origin of Illicitly Trafficked Nuclear Materials,” Analyst, Royal Society of Chemistry, 130 (2005), pp. 433–441 Production Reactor Types A. Glaser, Signatures of Weapon-grade Plutonium from Dedicated Production Reactors, 49th INMM Annual Meeting, July 13-17, 2008, Nashville, TN Production Reactor Types Graphite moderated Heavy-water moderated Driver fuel with external H2O cooled CO2 cooled H2O cooled D2O cooled DU targets United States Hanford Savannah River Russia “Tomsk-7” U.K. Calder Hall France G-Series Célestin China “Jiuquan” Israel Dimona India Cirus/NRX Dhruva Pakistan Khushab DPRK Yongbyon A. -
Fuels for Canadian Research Reactors
XA04C1592 FUELS FOR CANADIAN RESEARCH REACTORS M. A. Feraday Atomic Energy of Canada, Ltd. Chalk River, Ontario INTRODUCTION Originallywhen I was requested to attend the meetingit was to be as an observer. Last Friday David Stahl asked if I would make an informal presenta- tion on the Canadian situation. The remarks I will make will be of a general -nature and should not necessarily be construed as official policy of AECL. They will be personal observations on several aspects of the program. Although my 22 years experience in the nuclear field ranges from reactor operations, fuel development, and now designing of remotely operated fuel plants for gamma active 233U-Th fuels, I am not expert in the fields of reactor physics, reactor safety, and the political implications of changing the enrichment in our two large research reactors. So what I would like to do this morning is: - say a few words on the uranium silicide fuels for which we have significant fabrication, irradiationand defect performance experience. - describe the two Canadian high flux research reactors which use high enrichment uranium (HEU) and the fuels currently used in these reactors. - comment on the limited fabrication work we are doing on Al-U alloys to uranium contents as high as 40 wt%. This work is aimed at our fast neutron program. I will then try and apply this experience in general terms to the NRX and NRU designs of fuel. U3Si PROGRAM For a period of about 10 years AECL had a significant program looking into the possibility of developing U3Si as a high density replacement for the U02 pellet fuel in use in CANDU power reactors. -
Canada's Chalk River
Volume 15, No. 39 Published by BNL Personnel Office June 5,1962 EIGHTEENTH BROOKHAVEN LECTURE CANADA’S CHALK RIVER by JOHN BLEWETT, Accelerator Dept. Title: “Accelerators of the Future” With the following article on Canada’s Chalk River facility, the BULLETIN BOARD continues its series on BNL’s sister laboratories in this country and Lecture Hall, 8:00 p.m., Wed., June 13 similar laboratories abroad. A buffet supper ($2.75) will be served at the Brookhaven Center before the lecture, beginning ot 600 p.m. Reselva- tions should be made ot least one (day in advance by calling Ext. 2302 before 500 p.m., or Ext. 2453 in the evenings. Refreshments will be available in the Research Staff Lobby following the lecture. FOURTH PEGRAM LECTURESHIP This year, the Pegram Lectures will be given in June rather than in the autumn. The George B. Pegram Lecturer for 1962 is Professor Derek J. de Solla Price of Yale University, who is an eminent historian of science. In his lecture series, entitled “Little Science, Big Science,” Professor Price will consider the chang- ing circumstances in the life of the Night view of the ChalkRiver establishment of Atomic Energy of Canada Limited. scientist since the late nineteenth cen- tury and the profound effects which Canada’s main atomic research and development center is located at these changes have had on the behavior Chalk River, Ontario, and is operated by the crown company, Atomic Energy and attitude of scientists as well as on of Canada Limited. AECL is an agency of the federal Canadian government their organizations and publications. -
Risks of Operating Candu 6 Nuclear Power Plants: Gentilly Unit 2 Refurbishment and Its Global Implications
Risks of Operating Candu 6 Nuclear Power Plants: Gentilly Unit 2 Refurbishment and its Global Implications November 2008 BY GORDON R. THOMPSON Institute for Resource and Security Studies www.greenpeace.ca RISKS OF OPERATING ABSTRACT Operation of any nuclear power plant creates risks. CANDU 6 plants CANDU 6 NUCLEAR POWER PLANTS: pose additional risks arising from their use of natural uranium as fuel and Gentilly Unit 2 Refurbishment and its heavy water as moderator. A CANDU 6 reactor could experience a violent Global Implications power excursion, potentially leading to containment failure and a release of radioactive material to the environment. Spent fuel discharged from a CANDU 6 could be diverted and used to produce plutonium for nuclear BY GORDON R. THOMPSON weapons. Those risks are examined here with special attention to Hydro- Institute for Resource and Security Studies Quebec’s plan for refurbishment and continued operation of the Gentilly 2 plant. That action would lead to continued radiological risk in Quebec Prepared under the sponsorship of and could promote sales of CANDU 6 plants in other countries, thereby Greenpeace Canada contributing to an enhanced risk of nuclear-weapon proliferation. Hydro- Quebec’s plan also faces regulatory risks. Safety issues could increase the © Copyright November 2008 cost of refurbishing Gentilly 2, weakening an already marginal economic case for refurbishment. This report proposes an approach for systematic, GREENPEACE CANADA public assessment of the risks associated with Gentilly 2. 33 Cecil St. Toronto, Ontario ABOUT THE INSTITUTE FOR RESOURCE AND SECURITY STUDIES M5T 1N1 The Institute for Resource and Security Studies (IRSS) is an independent, www.greenpeace.ca nonprofit, Massachusetts corporation, founded in 1984.