A Comprehensive Approach to Elimination of Highly-Enriched
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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 ........................................................................................................ -
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. -
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. -
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 $. -
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. -
The Slowpoke Licensing Model
AECL—9981 CA9200276 AECL-9981 ATOMIC ENERGY ENERGIEATOMIQUE OF CANADA LIMITED DU CANADA LIMITEE THE SLOWPOKE LICENSING MODEL LE MODELE D'AUTORISATION DE CONSTRUIRE DE SLOWPOKE V.G. SNELL, F. TAKATS and K. SZIVOS Prepared for presentation at the Post-Conference Seminar on Small- and Medium-Sized Nuclear Reactors San Diego, California, U S A. 1989 August 21-23 Chalk River Nuclear Laboratories Laboratoires nucleates de Chalk River Chalk River, Ontario KOJ 1J0 August 1989 aout ATOMIC ENERGY OF CANADA LIMITED THE SLOWPOKE LICENSING MODEL by V.G. Snell, F. Takats and K. Szivos Prepared for presentation at the Post-Conference Seminar on Small- and Medium-Sized Nuclear Reactors San Diego, California, U.S.A. 1989 August 21-23 Local Energy Systems Business Unit Chalk River Nuclear Laboratories Chalk River, Ontario KOJ 1JO 1989 August ENERGIE ATOMIQUE DU CANADA LIMITED LE MODELS D'AUTORISATION DE CONSTRUIRE DE SLOWPOKE par V.G. Snell, F. Takats et K. Szivos Resume Le Systeme Energetique SLOWPOKE (SES-10) est un reacteur de chauffage de 10 MW realise au Canada. II pent fonctionner sans la presence continue d'un operateur autorise et etre implante dans des zones urbaines. II a des caracteristiques de surete indulgentes dont des echelles de temps transitoires de l'ordre d'heures. On a developpe, au Canada, un precede appele autorisation de construire "d'avance" pour identifier et resoudre les questions reglementaires au debut du processus. Du fait du marche possible, en Hongrie, pour le chauffage nucleaire urbain, on a etabli un plan d'autorisation de construire qui comporte 1'experience canadienne en autorisation de construire, identifie les besoins particuliers de la Hongrie et reduit le risque de retard d'autorisation de construire en cherchant 1'accord de toutes les parties au debut du programme. -
Workshop on Proposed Amendments to the Nuclear Security Regulations
Workshop on Proposed Amendments to the Nuclear Security Regulations Michael Beaudette Director Nuclear Security Division October 12, 2016 e-Doc: 5054938 nuclearsafety.gc.ca Focus of Today’s Workshop • Licensees currently listed in Schedule 2 of the Nuclear Security Regulations – Cameco, GE-Hitachi, Nordion, SRB Technologies • Licensees who process, use and store Category III nuclear material – examples include Slowpoke Reactors, McMaster Nuclear Reactor • Licensees and stakeholders who transport or arrange for the transport of nuclear material – examples include RSB Logistic, TAM International, Laurentide Forwarders Inc. Canadian Nuclear Safety Commission 2 Today’s Goals • Provide an overview of several proposed amendments that CNSC staff is considering making to the Nuclear Security Regulations (NSR) and receive preliminary feedback from stakeholders • Provide an opportunity for stakeholders to suggest additional areas for potential amendments to the NSR Please note that this is a CNSC staff assessment for prompting early discussion Canadian Nuclear Safety Commission 3 Objectives of Amendments • Ensure that the regulations continue to fulfill their role in effectively addressing Canada’s nuclear security • Ensure that Canada continues to fulfill its international obligations for the security of nuclear and radioactive materials Canadian Nuclear Safety Commission 4 Overview of the Regulatory Amendment process Canadian Nuclear Safety Commission 5 Context: Changes Since Last Amendments • Last major amendments to NSR published in 2006 • -
Minutes of the CNSC Meeting Held Wednesday and Thursday
December 9 and 10, 2009 Minutes of the Canadian Nuclear Safety Commission (CNSC) Meeting held Wednesday, December 9, 2009 beginning at 9:07 a.m. at the CNSC Headquarters, 14th floor, 280 Slater Street, Ottawa, Ontario. The meeting was adjourned at 6:45 p.m. on Wednesday, December 9 and reconvened on Thursday, December 10, 2009 at 9:05 a.m. at the same location. The public meeting was adjourned again at 12:37 p.m., reconvened at 3:32 p.m. and closed at 4:05 p.m. Present: M. Binder, President A. Graham C.R. Barnes A. Harvey R.J. Barriault M. J. McDill M. Leblanc, Secretary J. Lavoie, Senior General Counsel P. Reinhardt, Recording Secretary M. Young, Recording Secretary CNSC staff advisors were: P. Webster, F. Rinfret, P. Elder, K. Lafrenière, T. Schaubel, B.R. Ravishankar, L. Desaulniers., J. Schmidt, M. Ilin, J. Jaferi, G. Cherkas, S. Lei, M. Rinker and D. Werry Other contributors were: • Atomic Energy Canada Limited: W. Pilkington and A.J. White • Bruce Power Inc.: F. Saunders • Hydro-Québec: C. Gélinas • University of Alberta: G. Pavlich and M. J. M. Duke • Ecole Polytechnique de Montréal: G. Kennedy, G. Marleau and C. Chilian • Royal Military College of Canada: K. Nielsen and R. Weir • Saskatchewan Research Council: J. Muldoon, Y. Wo and W. Yuen • Ontario Power Generation Inc.: M. Elliott and R. Leavitt, • Province of Ontario: S. Imbrogno • Cameco Corporation: A. Thorne, C. Astles, A. Oliver, D. Clark, J. Degraw, K. Vetor, R. Peters, A. Kodarin, M. Longinov, T. Rouse and M. Garrard • NB Power Nuclear: G. -
Q L'energieatomique of Canada Limited Vasv Du Canada Limitee
AECL-8252 ATOMIC ENERGY flF*~Q L'ENERGIEATOMIQUE OF CANADA LIMITED VASV DU CANADA LIMITEE SLOWPOKE: THE FIRST DECADE AND BEYOND SLOWPOKE: La premiere decennie et apres J.W. HILBORN and G.A. BURBIDGE Chalk River Nuclear Laboratories Laburatoires nucleates de Chalk River Chalk River, Ontario October 1983 octobre ATOMIC ENERGY OF CANADA LIMITED SLOWPOKE: The First Decade and Beyond by J.U. Hilborn and G.A. Burbidge* *Radiochemical Company Reactor Physics Branch Chalk River Nuclear Laboratories Chalk River, Ontario KOJ 1J0 Canada October 1983 AECL-8252 L'ENERGIE ATOMIQUE DU CANADA, LIMITEE SLOWPOKE: La premiere décennie et aprës* par J.W. Hilborn et G.A. Burbridge** Resume Depuis le démarrage du premier réacteur SLOWPOKE dans les Laboratoires nucléaires de Chalk River en 1970, six réacteurs de recherche SLOWPOKE-2 ont été installés ailleurs au Canada et un septième est en voie d'instal- lation en Jamaïque. Conçu principalement pour les analyses par activation neutronique, le SLOWPOKE de 20 kW produit un flux de neutrons thermiques de 10i2 n.cnr^s"' dans cinq alvéoles destinées aux échantillons situées dans un réflecteur en béryllium entourant le coeur du réacteur. Il y a cinq autres alvéoles dans le réflecteur rempli d'eau situé ä l'extérieur du réflecteur en béryllium. Le SLOWPOKE a d'excellentes propriétés en matière de sécurité provenant de la température négative et des coefficients de vide du coeur, d'une réactivitê maximale limitée et de l'accès interdit au coeur par les utilisateurs. Il en résulte que le réacteur n'a pas besoin d'un système d'arrêt automatique, de chambres d'ionisation de neutrons ou d'instruments de démarrage â faible puissance. -
Proceedings of the Topical Session of the Rwmc 40Th Meeting On
Unclassified NEA/RWM(2007)9 Organisation de Coopération et de Développement Economiques Organisation for Economic Co-operation and Development 18-Jun-2007 ___________________________________________________________________________________________ English - Or. English NUCLEAR ENERGY AGENCY RADIOACTIVE WASTE MANAGEMENT COMMITTEE Unclassified NEA/RWM(2007)9 PROCEEDINGS OF THE TOPICAL SESSION OF THE RWMC 40TH MEETING ON: APPROACHES AND PRACTICES IN DECOMMISSIONING OF FACILITIES AND MANAGEMENT OF RADIOACTIVE WASTE FROM NON-NUCLEAR FUEL CYCLE RELATED ACTIVITIES Held at the NEA Offices in Issy-les-Moulineaux, France on 14 March 2007 English - Or. English JT03229237 Document complet disponible sur OLIS dans son format d'origine Complete document available on OLIS in its original format NEA/RWM(2007)9 2 NEA/RWM(2007)9 FOREWORD Many activities in modern society involve the use of radioactive materials necessitating dedicated facilities for their production, application, and storage. This applies universally and, regardless of whether or not they are involved in nuclear fuel cycle related activities, all countries need frameworks for decommissioning of contaminated facilities and the construction of facilities for radioactive waste management in a manner that does not impact unduly on society in terms of safety and costs. Countries with nuclear power programmes are perhaps more likely to have in place the necessary infrastructure for dealing with non-power wastes. Nevertheless, a general concern exists about whether enough attention has been paid to small users and/or producers of radioactive materials, whether in academia, in medicine or in industry. Legacy waste is also an important issue in some countries. The exchange of the information about experiences of member countries in this area may thus be expected to have widespread benefits. -
Whiteshell Laboratories – Manitoba’S Contribution to Nuclear Engineering in Canada
Whiteshell Laboratories – Manitoba’s Contribution to Nuclear Engineering in Canada Prepared By Chris Saunders, P. Eng. and Ray Sochaski, P.Eng; Life Member Atomic Energy of Canada Limited (AECL) established a role in Manitoba in 1963 when the Whiteshell Nuclear J.L. Gray Research Establishment (WNRE; later renamed Whiteshell James Lorne Gray was born in Brandon, Laboratories) first took shape. WNRE was Canada’s second Manitoba in 1913. After nuclear science research and development laboratory and public school in the first facility of its kind in western Canada. Through its Winnipeg, he graduated years of operation, the people of the WNRE made with a Masters in Mechanical Engineering significant contributions to the science and engineering from the University of knowledge of Canada’s nuclear industry. This article Saskatchewan in 1938. He highlights just a few of these many accomplishments. joined the Royal Canadian Air Force in 1939. In the Beginning Mr. Gray’s scientific career began at the National Research In the late 1950s AECL’s managers thought Chalk River Council in 1948. He was assigned to the “Chalk River” Laboratories (CRL) was nearing the saturation point. A project. He advanced to become President of AECL in 1958. For the next 16 years he led the corporation through quick survey indicated that three provinces were lacking an impressive growth period that saw Canada become a federal research facilities: Newfoundland, Alberta and leader in nuclear engineering and technologies. Manitoba. Newfoundland, it was felt was not an option at Mr. Gray was appointed a Companion of the Order of the time, having joined Canada less than ten years Canada in 1969 and was awarded the Professional previously in 1949. -
Refuelling the Slowpoke-2 Reactor at Ecole Polytechnique: Procedure and Proposed Experiments
REFUELLING THE SLOWPOKE-2 REACTOR AT ECOLE POLYTECHNIQUE: PROCEDURE AND PROPOSED EXPERIMENTS. o G. KENNEDY AND G. MARLEAU Institut de genie nucleaire _^s O Ecole Polytechnique de Montreal, Montreal, Quebec H3C 3A7 Bf e-mail: [email protected] ^^ ABSTRACT As the expected lifetime of the present fuel in the SLOWPOKE-2 reactor at Ecole Polytechnique de Montreal was seen to approach, a project was initiated which will lead to the refueling of the reactor in 1997. Two aspects of this project require major development work: the defueling and fuel loading procedures need to be revised since this is the first time a SLOWPOKE reactor will be refueled; work is also required to bring safety analysis and documentation in line with recent regulatory requirements. Here, we present the proposed overall refueling strategy and discuss the changes in the operation of the core resulting from the use of low-enriched fuel. Additional experiments, which should be carried out during commissioning, are also analyzed. I. Introduction The SLOWPOKE-2 reactor at Ecole Polytechnique de Montreal has operated since 1976 with the original fuel which consists of 0.8 kg of 93% enriched Uranium (HEU). The 296 fuel pins contain Uranium-Aluminium alloy with Aluminium cladding. The core is surrounded by a Beryllium reflector and is moderated and cooled by light water which circulates by natural convection. The reactor is used for research involving neutron activation analysis and the use of radioactive tracers as well as for teaching.M As the lifetime of the present fuel was seen to approach, a project which was initiated three years ago will lead to the refueling of the reactor in 1997.