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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. -
Analysis of Zirconium and Nickel Based Alloys and Zirconium Oxides
NET318_proof ■ 22 February 2017 ■ 1/7 Nuclear Engineering and Technology xxx (2017) 1e7 Available online at ScienceDirect 65 66 1 67 2 Nuclear Engineering and Technology 68 3 69 4 70 5 journal homepage: www.elsevier.com/locate/net 71 6 72 7 73 8 74 9 Original Article 75 10 76 11 Analysis of Zirconium and Nickel Based Alloys and 77 12 78 13 Zirconium Oxides by Relative and Internal 79 14 80 15 81 16 Monostandard Neutron Activation Analysis 82 17 83 18 Q1 Methods 84 19 85 20 * 86 21 a b, a,1 Q15 Q2Amol D. Shinde , R. Acharya , and A.V.R. Reddy 87 22 88 Q3 a Analytical Chemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India 23 89 b Radiochemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India 24 90 25 91 26 92 article info abstract 27 93 28 94 29 Article history: Background: The chemical characterization of metallic alloys and oxides is conventionally 95 30 Received 9 March 2016 carried out by wet chemical analytical methods and/or instrumental methods. Instru- 96 31 Received in revised form mental neutron activation analysis (INAA) is capable of analyzing samples nondestruc- 97 32 1 August 2016 tively. As a part of a chemical quality control exercise, Zircaloys 2 and 4, nimonic alloy, and 98 33 99 34 Accepted 19 September 2016 zirconium oxide samples were analyzed by two INAA methods. The samples of alloys and Available online xxx oxides were also analyzed by inductively coupled plasma optical emission spectroscopy 100 35 101 (ICP-OES) and direct current Arc OES methods, respectively, for quality assurance pur- 36 102 Keywords: poses. -
Separating Indian Military and Civilian Nuclear Facilities
Separating Indian Military and Civilian Nuclear Facilities Institute for Science and International Security (ISIS) By David Albright and Susan Basu December 19, 2005 The agreement announced on July 18, 2005 by President George Bush and Prime Minister Manmohan Singh regarding the establishment of a U.S.-India “global partnership” will require changes to U.S. non-proliferation laws and policies and could dramatically increase nuclear and nuclear-related commerce with India. Part of this agreement is an Indian commitment to separate its civil and military nuclear programs and put declared civil facilities under international safeguards. Safeguards should apply in perpetuity, with minor, standard exceptions that do not include use in nuclear explosives or weapons. In addition, safeguarded nuclear material should not co-mingle with unsafeguarded nuclear material in any facility, unless this unsafeguarded nuclear material also comes under safeguards. This latter condition is an example of “contamination,” a key principle of safeguards. Although these conditions do not appear to have been accepted by India, they are necessary to prevent civil nuclear cooperation from benefiting India’s nuclear weapons program. To accomplish these goals, India needs to place all its nuclear facilities not directly associated with nuclear weapons production or deployment under safeguards. India has many civil nuclear facilities in this category. In addition, India should place its nuclear facilities associated with its naval nuclear fuel cycle under international safeguards. Exempting such naval-related facilities from safeguards would undermine efforts to safeguard such facilities in non-nuclear weapon states party to the Nuclear Non-Proliferation Treaty. Brazil accepted safeguards on its prototype naval reactor and its enrichment plants at Aramar dedicated to the production of naval reactor fuel. -
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. -
India's Stocks of Civil and Military Plutonium and Highly Enriched Uranium, End 2014
PlutoniumPlutonium andand HighlyHighly EnrichedEnriched UraniumUranium 20152015 INSTITUTEINSTITUTE FOR FOR SCIENCE SCIENCE AND AND INTERNATIONAL INTERNATIONAL SECURITY SECURITY India’s Stocks of Civil and Military Plutonium and Highly Enriched Uranium, End 20141 By David Albright and Serena Kelleher-Vergantini November 2, 2015 1 This report is part of a series on national and global stocks of nuclear explosive materials in both civil and military nuclear programs. This work was generously funded by a grant from the Nuclear Threat Initiative (NTI). This work builds on earlier work done at ISIS by one of the authors. 440 First Street NW, Suite 800, Washington, DC 20001 TEL 202.547.3633 Twitter @TheGoodISIS E-MAIL [email protected] • www.isis-online.org Contents Summary .............................................................................................................................................. 2 1. India’s Civil Plutonium Stockpile .................................................................................................... 3 1.1 Civil Plutonium Production ........................................................................................................ 3 1.2 Plutonium Separation ................................................................................................................. 5 1.2.1 India’s Fast Breeder Reactors .............................................................................................. 6 1.3 Unirradiated Plutonium Inventory ............................................................................................. -
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 -
Preparation and Submission of a Manuscript for the Proceedings
IAEA-TM-38728 (2010) OPERATION AND UTILIZATION OF INDIAN RESEARCH REACTOR DHRUVA SAMIR KUMAR MONDAL Bhabha Atomic Research Centre, Mumbai, India [email protected] 1. INTRODUCTION The role of research reactors for the development of the nuclear programme of any country is well established. Research reactors are utilized to produce radioisotopes and offer irradiation facilities for testing various nuclear fuel and structural materials. Apart from providing a large volume neutron source for carrying out a variety of experiments, the research reactor forms the basic training facility for grooming scientists and engineers for various aspects of a nuclear programme. India’s fifth research reactor Dhruva, which became critical on 8 August 1985, is a natural uranium fuelled, heavy water moderated and cooled thermal research reactor with a rated power level of 100 MW and a maximum thermal neutron flux of 1.8×1014 cm-2s-1. The indigenously designed and built reactor is located at the Bhabha Atomic Research Centre (BARC) in Trombay. Dhruva is a product of technological initiatives taken in India during the 1970s with a totally indigenous effort when a need was felt for a research reactor having a high neutron flux to meet the growing demands of research and development. In addition, large scale production of radioisotopes with high specific activity was possible with the commissioning of Dhruva. This high flux reactor was designed and built with many innovative features which were being considered for our power reactors at that time. The reactor has a vertical core and employs natural metallic uranium in seven-pin cluster fuel assemblies installed in Zircaloy guide tubes in a stainless steel reactor vessel. -
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. -
Nuclear Engineering and Technology 49 (2017) 562E568
Nuclear Engineering and Technology 49 (2017) 562e568 Available online at ScienceDirect Nuclear Engineering and Technology journal homepage: www.elsevier.com/locate/net Original Article Analysis of Zirconium and Nickel Based Alloys and Zirconium Oxides by Relative and Internal Monostandard Neutron Activation Analysis Methods * Amol D. Shinde a, Raghunath Acharya b, , and Annareddy V.R. Reddy a a Analytical Chemistry Division, Mod Labs, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India b Radiochemistry Division, Radiological Laboratories, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085, India article info abstract Article history: Background: The chemical characterization of metallic alloys and oxides is conventionally Received 9 March 2016 carried out by wet chemical analytical methods and/or instrumental methods. Instru- Received in revised form mental neutron activation analysis (INAA) is capable of analyzing samples nondestruc- 1 August 2016 tively. As a part of a chemical quality control exercise, Zircaloys 2 and 4, nimonic alloy, and Accepted 19 September 2016 zirconium oxide samples were analyzed by two INAA methods. The samples of alloys and Available online 6 February 2017 oxides were also analyzed by inductively coupled plasma optical emission spectroscopy (ICP-OES) and direct current Arc OES methods, respectively, for quality assurance pur- Keywords: poses. The samples are important in various fields including nuclear technology. AES Methods: Samples were neutron irradiated using nuclear reactors, and the radioactive assay Chemical Quality Control was carried out using high-resolution gamma-ray spectrometry. Major to trace mass IM-NAA fractions were determined using both relative and internal monostandard (IM) NAA INAA methods as well as OES methods.