DOCSLIB.ORG

FNCA Research Reactor Network Catalogue 2016

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
FNCA Research Reactor Network Catalogue 2016 FNCA Research and Test Reactors Catalogue December 2016 FNCA Research Reactor Network Project FNCA Research Reactor Network Project, 2016 CONTENTS 1. OPAL ………………………………………………………………………………….. 1 Australian Nuclear Science and Technology Organisation (ANSTO) 2. 3 MW TRIGA Mark-II Research Reactor …………………………………………… 3 BAEC (Bangladesh Atomic Energy Commission) 3. CARR (China Advance Research Reactor) ……. ………………………………… 12 CIAE (China Institute of Atomic Energy) 4. RSG-GAS Reactor ………………………………………………….…………………18 BATAN (Indonesian Nuclear Energy Agency) 5. JMTR (Japan Materials Testing Reactor) ………………………………………… 22 JAEA (Japan Atomic Energy Agency) 6. JRR-3 (Japan Research Reactor No.3) ………………………………………..……35 JAEA (Japan Atomic Energy Agency) 7. KUR (Kyoto University Research Reactor) …………………..…… To be added Kyoto University Research Reactor Institute 8. HANARO (High-flux Advanced Neutron Application ReactOr) .…….…….…… 40 KAERI (Korea Atomic Energy Research Institute) 9. WWR-K ……………………………………………………………..… To be added National Nuclear Center of the Republic of Kazakhstan 10. RTP (The Reactor TRIGA PUSPATI) …………………………….………………… 44 Malaysian Nuclear Agency 11. TRR-1/M1 (Thailand's Research Reactor 1, Modification 1) ….….….….….…. 49 TINT (Thailand Institute of Nuclear Technology) 12. DNRR (Dalat Nuclear Research Reactor) ………………………………………….54 DRNI, VINATOM (Vietnam Atomic Energy Institute) i FNCA Research Reactor Network Project, 2016 FNCA Research and Test Reactors Catalogue Reactor Name: OPAL Organization: Australian Nuclear Science and Technology Organisation (ANSTO) Australian Nuclear Science and Technology Organisation (ANSTO) Locked Bag 2001, Kirrawee DC, NSW, 2234, Australia Contact person : David Vittorio e-mail: [email protected] 1. General information 2. Reactor and Facilities OPAL is a 20 MW, multipurpose open pool reactor. The reactor facility incorporates five horizontal primary Construction of OPAL commenced in 2002 and first neutron beams, two of which are optimized for thermal criticality was achieved on 12 August 2006. OPAL is flux and two which are optimized for cold neutrons. light water cooled and moderated. The reactor core is Cold neutrons are generated from a liquid deuterium surrounded by a cylindrical vessel containing heavy cold neutron source which sits adjacent to the core. water. The reactor core consists of 16 plate type fuel Thirteen neutron beam instruments are located within assemblies controlled by five control rods which also a dedicated neutron guide hall. These instruments are: act as the fast acting first shutdown system. • High-Resolution Powder Diffractometer The reactor is cooled by forced circulation of light • High-Intensity Powder Diffractometer water during operation and natural convection during • Laue Diffractometer shutdown. • Strain Scanner • For further information see www.ansto.gov.au Neutron Reflectometer • Small-Angle Neutron Scattering • Thermal Neutron 3-Axis Spectrometer • Ultra Small-Angle Neutron Scattering • Time-of-Flight Spectrometer • Neutron Radiography/Imaging/ Tomography • Cold Neutron 3-Axis Spectrometer • Small-Angle Neutron Scattering Instrument • High-Resolution Backscattering Irradiations are performed in vertical facilities penetrating into the heavy water reflector vessel which surrounds the core. A variety of irradiation facilities are provided to allow for a range of irradiations to be undertaken depending on irradiation time, physical target size and cooling capacity required by the target. The primary use of the irradiation facilities are for radioisotope production, specifically molybdenum-99, and the neutron transmutation doping of silicon. Irradiation facilities are also provided for materials research and delayed neutron activation analysis and neutron activation analysis. Opal Reactor cross-section 3. Related engineering and research infrastructure 1 FNCA Research Reactor Network Project, 2016 3.1 Experimental material logistics Significant research based achievements have been highlighted in regards to the utilisation of neutron beam 3.2 Hot cells, PIE facilities facilities and instruments of the OPAL reactor. The Hot cell facilities are available within the reactor area to recent publication of Neutron News (Volume 27, issue support the preparation and logistics management of April/May/June 2016) has reported on a number of irradiated targets and samples. PIE, hot cells and scientific highlights with regards to neutron beam facilities are available at the ANSTO Lucas Heights site. instrument usage and outcomes. 3.3 Capabilities to design and manufacture 5. Other useful/ important information experimental devices and measurement systems REFERENCES including human resources development [1] www.ansto.gov.au 4. Recent achievements OPAL Reflector Vessel 2 FNCA Research Reactor Network Project, 2016 FNCA Research and Test Reactors Catalogue Reactor Name: 3 MW TRIGA Mark-II Research Reactor Organization: BAEC (Bangladesh Atomic Energy Commission) Bangladesh Atomic Energy Commission CSO and Head, RPED, INST, AERE, GPO BOX #3787, DHAKA-1000, Bangladesh Contact Person : Dr. Md. Jahirul Haque Khan, e-mail : [email protected] 1. General Information 1986. Since then, the reactor is designed for The 3 MW TRIGA Mark-II [1] research multipurpose uses like manpower training, radio- reactor is the only nuclear reactor facility in isotope production and various R&D activities in the Bangladesh satisfying its academic, training and field of neutron activation analysis (NAA), neutron research objectives and it is an excellent source of radiography (NR) and neutron scattering (NS) neutron. The Bangladesh Atomic Energy Commission experiments. It is a light-water-cooled, graphite- (BAEC) has been operating the TRIGA (Training, reflected, cylindrical shaped pool type research reactor, Research, Isotope production, General Atomics) which uses uranium-zirconium hydride fuel elements Mark-II research reactor (shown in Fig. 1) with a in a circular grid array. The array also contains maximum thermal flux 7.46x10 13 n/cm 2/sec in the graphite dummy elements, which serves to reflect center of the core at full power 3 MW since September neutrons back into the core. T-Training R-Research I-Isotope G-General A-Atomic Fig. 1: 3 MW TRIGA Mark-II Research Reactor The core is situated near the bottom of water filled tank up to $2.00 having a half–maximum pulse width of and the tank is surrounded by a concrete bio-shield, nearly 18.6 milliseconds. which acts as a radiation shield and structural support. The unique safety feature of the TRIGA As the reactor deals with the Fission Chain Reaction, reactor is the prompt negative temperature coefficient of it is an excellent source of neutrons and gamma reactivity of its U-ZrH fuel-moderator material. This radiation. The reactor is licensed by the Bangladesh characteristic allows sudden large insertions of Atomic Energy Regulatory Authority (BAERA) to reactivity in which the power level increases many operate at a maximum steady state power of 3 MW thousand times on periods of less than 2.0 msec. The (thermal) and can also be pulsed up to a peak power of control is based on the negative temperature coefficient about 852 MW with a maximum reactivity insertion of of reactivity, which decreases the power level to normal 3 FNCA Research Reactor Network Project, 2016 operating values in a fraction of a second. The same levels are so low due to vertical water shield above the characteristics also restrict the upper steady state core that personnel can view the core and experimental thermal power level that may be obtained with a given devices with complete safety during pulsed or amount of fuel. Thus, both transient and steady state steady-state operation. The principal design parameters operation have inherent safeguards which do not require of the reactor are shown in Table 1. manual, electronic or mechanical control. Radiation Table 1: Principal Design Parameters of the TRIGA Mark-II Research Reactor. Sl. No. Principal Design Parameters [1] 1. Reactor type TRIGA Mark-II 2. Maximum steady state power level 3 MW 3. Maximum pulse 1.4% δk/k, $ 2.00, 852 MW 4. Fuel moderator material U-ZrH 1.6 5. Uranium content 20 wt% 6. Uranium enrichment 19.7% 235 U 7. Burnable poison 0.47 wt% 166 Er and 166 Er 8. Shape Cylindrical 9. Overall length of fuel 38.1 cm (15 inch) 10. Outside diameter of the fuel 3.63 cm (1.43 inch) 11. Cladding material Type 304 stainless steel 12. Total reactivity worth of control rods 10% δk/k 13. Number of control rods 6 2. Reactor and Facilities The reactor is housed in a hall of 23.5 m × 20.12 m having a height of 17.4 m. The reactor tank (which is also called the pool liner) accommodates the reactor core. The reactor core is located near the bottom of the reactor tank (shown in Fig. 2). The tank is made of aluminum alloy of type 6061-T6 which is installed inside the reactor shield structure. The length and diameter of the tank is 8.23 m and 1.98 m. The tank is filled up with 24,865 liters of de- mineralized water. The reactor core (shown in Fig. 3) consists of 100 fuel elements (93 standard fuel elements, 5 fuel follower control rods (FFCR) and 2 instrumented fuel elements), 6 control rods (5 FFCR and 1 air follower control rod), 18 graphite dummy elements, 1 Dry Central Thimble, 1 pneumatic transfer system irradiation terminus (Rabbit system) and 1 Am-Be neutron source (strength: 3 Ci). All these elements are placed and supported in-between two 55.25 cm diameter grid plates and arranged in a hexagonal lattice. The TRIGA reactor is equipped
Load more

Recommended publications
  • 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.
    [Show full text]
  • 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 $.
    [Show full text]
  • 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.
    [Show full text]
  • 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.
    [Show full text]
  • Digital Automatic Control System for the TRIGA Reactor Susumu Harasawa Institute for Atomic Energy, Rikkyo University 2
    Digital Automatic Control System for the TRIGA Reactor Susumu Harasawa Institute for Atomic Energy, Rikkyo University 2-5-1, Nagasaka, Yokosuka, 240-01, Japan Mohamad Amin Sharifuldin, Syed Nahar Syed Hussin Shahabudin Unit Tenaga Nuklear, Kompleks PUSPATI, 43000 Kajang , Selangor, Malaysia and Kunishiro Mori, Sadayuki Uchiyama Clear Pulse Co. Ltd . 6 - 25 - 17, Chuuoo, Oota-ku, Tokyo, 143 , Japan 1. INTRODUCTION One of the authors has designed a digital automatic control system with two sets of comparators for the TRIGA reactor of the Rikkyo University " . The control system has been designed in resemblence with manual operation of the reactor. The fundamental idea was that the time interval of the digital control action depends on the deviation between the power output and the demand power. In the case of the Rikkyo University Reactor, when the deviation is smaller than ± 0.2 %, no action occurs, when the deviation exceeds ± 0.2 % but below ± 3. 5 %, a regurating rod responds for 0.1 second with stepwise movement at an interval of 1 second, and when the deviation exceeds ± 3.5 % the regulating rod moves continuously. These actions has been materialized by using two sets of comparators and a pulse generator. Another control system for the PUSPATI TRIGA Reactor applying similar idea was designed and tested in 1987. The control system has one comparator which detects the difference of the reactor output and demand power as conventional control systems have, and the time interval of the control action of the newly designed system is determined by a voltage-to-frequency-convertor. The idea and results of the automatic control systems for the Rikkyo University Reactor and PUSPATI TRIGA Reactor are discussed below.
    [Show full text]
  • Supplement Analysis for the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program
    DOE/EIS-0218-SA-8 SUPPLEMENT ANALYSIS FOR THE FOREIGN RESEARCH REACTOR SPENT NUCLEAR FUEL ACCEPTANCE PROGRAM APRIL 2019 \?f1l ~ : ~ National Nuclear Security Administration U.S. Department of Energy National Nuclear Security Administration Washington, DC Supplement Analysis for the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program TABLE OF CONTENTS Page 1.0 INTRODUCTION AND BACKGROUND ........................................................................................... 1 1.1 Policy on Exemptions ..... ................................................ .... .................................................... 2 1.2 Statement of Intent Between the United States and Japan .................. .. .................... ......... 3 1.3 HEU Shipments ..... .. ............................................................................................................... 3 1.4 Training Research Isotope General Atomics (TRIGA) Fuel .................................... ................ 4 2.0 PURPOSE AND NEED, AND PROPOSED ACTION ............................................................................ 4 2.1 Purpose and Need .................................................... ...................... ....................................... 4 2.2 Proposed Action ............ .. ...................... ....................................................................... .. .... ... 4 2.3 Description of Activities ......................................................................................................... 4 3.0 AFFECTED
    [Show full text]
  • Report on Latin-American Activities in Nuclear Physics
    Report on Latin-American Activities in Nuclear Physics Alinka Lépine-Szily Instituto de Física-USP São Paulo, Brazil IUPAP Working Group WG.9 AGM Adelaide Australia, September 11, 2016 ALAFNA http://www.alafna.net/ The “Association of Latin American Nuclear Physics and Applications” (ALANPA) was formed in Santiago, Chile on Dec. 19, 2009, by representatives of Argentina, Brazil, Chile, Colombia, Mexico, Peru and Venezuela. In Spanish is called “Asociación Latino Americana de Física Nuclear y Aplicaciones” ALAFNA In Portuguese is called “Associação Latino Americana de Física Nuclear e Aplicações” ALAFNA Chairs of ALAFNA, reelected in 2015 at Medellin: • Andrés Kreiner (Argentina) • Alinka Lépine-Szily (Brazil) Executive Board • Fernando Cristancho (Universidad Nacional, Bogotá) Colombia • Raul Donangelo (Universidad de la República, Montevideo), Uruguay • Paulo Gomes (Universidad Federal Fluminense, Rio de Janeiro), Brasil • Andrés Kreiner (Tandar, CNEA, Buenos Aires), Argentina • Alinka Lépine-Szily (Universidade de Sao Paulo, Sao Paulo), Brasil ALAFNA homepage is installed: www.alafna.net Next meeting of ALAFNA: together with next XII LASNPA, Nov. 2017 in Havana,Cuba Nuclear science installations in Latin America Research reactors: Argentina 6 in operation, 1 in construction CAREM • RA-0, built 1964, 0.01 kWt, tank type, owned and operated by Universidad Nacional de Cordoba • RA-1 built 1957, 40 kWt, tank type. • RA-2, built 1965, 0.03 kWt, critical assembly type (shut down on 1983/09/01) • RA-3, built 1963, 5,000 kWt, pool type. • RA-4 (former SUR-100), built 1971, HOMOG type, owned and operated by Universidad Nacional de Rosario • RA-6, built 1978, 500 kWt, pool type. • RA-8, built 1986, 0.01 kWt, critical assembly type • CAREM prototype 25 Mwe, under construction 2 October 2014, expected completion 2017.
    [Show full text]
  • Thermal Hydraulic Analysis of 3 MW TRIGA Research Reactor of Bangladesh Considering Different Cycles of Burnup
    M.H. Altaf and AtomN.H. BadrunIndonesia / AtomAtom Vol. Indonesia40Indonesia No. 3 (2014) Vol. 40 107 No. - 1123 (2014) 107 - 112 Thermal Hydraulic Analysis of 3 MW TRIGA Research Reactor of Bangladesh Considering Different Cycles of Burnup M.H. Altaf and N.H. Badrun* Reactor Physics and Engineering Division (RPED), Institute of Nuclear Science and Technology (INST) Atomic Energy Research Establishment (AERE), Ganakbari, Savar, Dhaka-1349, Bangladesh A R T I C L E I N F O A B S T R A C T Article history: Burnup dependent steady state thermal hydraulic analysis of TRIGA Mark- Received 09 September 2014 II research reactor has been carried out utilizing coupled point kinetics, Received in revised form 21 December 2014 neutronics and thermal hydraulics code EUREKA-2/RR. From the previous Accepted 22 December 2014 calculations of neutronics parameters including percentage burnup of Keywords: individual fuel elements performed so far for 700 MWD burnt core of TRIGA reactor TRIGA reactor showed that the fuel rod predicted as hottest at the Burnup beginning of cycle (fresh core) was found to remain as the hottest until Thermal hydraulic 200 MWD of burn, but, with the progress of core burn, the hottest rod was EUREKA-2/RR found to be shifted and another rod in the core became the hottest. The present study intends to evaluate the thermal hydraulic parameters of these hottest fuel rods at different cycles of burnup, from beginning to 700 MWD core burnt considering reactor operates under steady state condition. Peak fuel centerline temperature, maximum cladding and coolant temperatures of the hottest channels were calculated.
    [Show full text]
  • Assessing the Risk of Terrorist Attacks on Nuclear Facilities Summary
    POST Report 222 July 2004 Assessing the risk of terrorist attacks on nuclear facilities Summary Assessing the risk of terrorist attacks on nuclear facilities July 2004 Report 222 Summary The events of September 11th 2001 heightened concerns over the potential for terrorist attacks on nuclear facilities. The purpose of this report is to provide Parliamentarians with an overview of what is publicly known about the risks and the consequences of such an attack, either at a facility in the UK, or overseas, with very direct impacts in the UK. This report identifies the main issues of concern according to reports in the public domain, and highlights areas where understanding is limited due to lack of publicly available information. The key points made in this report are as follows: • There is sufficient information in the public domain to identify possible ways terrorists might bring about a release of radioactive material from a nuclear facility. However this information is not sufficient to draw conclusions on the likelihood of a successful attack, or the size and nature of any release. • After September 11th 2001 additional protection measures have been put in place to increase security and to strengthen emergency planning at and around nuclear facilities. However, full details are not in the public domain. • Nuclear power plants were not designed to withstand some forms of terrorist attack, such as large aircraft impact, but existing safety and security regimes provide some defence. • Published reports suggest that, in a worst case scenario, the impact of large aircraft on certain facilities could cause a significant release of radioactive material with effects over a wide area.
    [Show full text]
  • Appendix E Agreements for Cooperation with Foreign Countries
    OFFICIAL USE ONLY - DRAFT AGREEMENTS FOR COOPERATION WITH FOREIGN COUNTRIES APPENDIX E AGREEMENTS FOR COOPERATION WITH FOREIGN COUNTRIES This appendix provides information on the quantities of HEU exported to foreign countries under international agreements for cooperation for peaceful uses of atomic energy. Under these agreements, the U.S. exported HEU to foreign countries for use in research applications, primarily as fuel for research reactors. As part of these agreements, the U.S. agreed to accept the return of this material primarily in the form of spent nuclear fuel. This appendix does not include HEU exported to foreign countries under mutual defense agreements and the acquisition of HEU from the former Soviet Republic of Kazakhstan. For the purposes of this report, information on foreign countries is broken out into four geographical regions: (1) Middle East and South Africa, (2) Europe, (3) North and South America, and (4) Asia and Australia. Countries that are members of the International Atomic Energy Agency (IAEA) and countries that have signed the Treaty on the Non- Proliferation of Nuclear Weapons (NPT)12 are identified. HEU Transfers to Foreign Countries BACKGROUND First destination does not mean that the receiving country was the The U.S. began exporting HEU in the 1950s as part of ultimate destination for the U.S.- origin HEU but, in fact, is the first President Eisenhower’s “Atoms for Peace” program. A foreign country to receive the series of agreements and treaties between the U.S. and material. Retransfers of U.S.-origin HEU many foreign countries allowed the export of nuclear from one foreign country to materials and technology to assist the countries in nuclear another are not accounted for in this report.
    [Show full text]
  • Topical Issues in Nuclear Safety
    XA0102762 ~O?J| INTERNATIONAL ATOMIC ENERGY AGENCY Topical Issues in Nuclear Safety Vienna, Austria 3-6 September 2001 IAEA-CN-82 PLEASE BE AWARE THAT ALL OF THE MISSING PAGES IN THIS DOCUMENT WERE ORIGINALLY BLANK NOTE The International Atomic Energy Agency is organizing an International Conference on Topical Issues in Nuclear Safety, to be held in Vienna, Austria, from 3 to 6 September 2001. This book contains concise contributed papers submitted on issues falling within the thematic scope of the Conference which were accepted by the Conference Programme Committee for consideration at the Conference. The material compiled in this book has not been edited by the editorial staff of the IAEA. However, certain modifications were made: a unified format was adopted for all papers and corrections were made in the text where required. It is intended that, after the Conference, the contents of this book will be published in the form of a CD ROM as part of the proceedings of the Conference. Authors wishing to make slight modifications or corrections to their paper are encouraged to contact the Conference Secretariat. The views expressed in the papers are the responsibility of the named authors. These views are not necessarily those of the Governments of Member States. Neither the IAEA nor Member States assume any responsibility for consequences which may arise from the use of information contained in this book. CONTENTS Topical Issue 1: Risk-informed decision making Regulatory approach to risk informed decision making in India (IAEA-CN-82/17) S.K. Chande, J. Koley 3 Risk concepts in UK nuclear safety decision-making (IAEA-CN-82/18) P.W.M.
    [Show full text]
  • Testing of a Transport Cask for Research Reactor Spent Fuel
    2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 TESTING OF A TRANSPORT CASK FOR RESEARCH REACTOR SPENT FUEL Rogério P. Mourão1, Luiz Leite da Silva1, Carlos A. Miranda2, Miguel Mattar Neto2, José F. A. Quintana3, Roberto O. Saliba3 and Oscar E. Novara4 1 Centro de Desenvolvimento da Tecnologia Nuclear Av. Pres. Antônio Carlos, 6.627 Campus UFMG - Pampulha 31.270-901 Belo Horizonte, MG [email protected], [email protected] 2 Instituto de Pesquisas Energéticas e Nucleares Av. Professor Lineu Prestes 2242 05508-000 São Paulo, SP [email protected], [email protected] 3 Centro Atómico Bariloche Comisión Nacional de Energía Atómica Avenida Exequiel Bustillo 9500 R8402AGP Bariloche, Argentina [email protected] , [email protected] 4 Centro Atómico Constituyentes Comisión Nacional de Energía Atómica Avenida Gral. Paz No. 1499/1650 San Martin C1429BNP Buenos Aires, Argentina [email protected] ABSTRACT Since the beginning of the last decade three Latin American countries which operate research reactors – Argentina, Brazil and Chile – have been joining efforts to improve the regional capability in the management of spent fuel elements from the reactors operated in the region. As a step in this direction, a packaging for the transport of irradiated fuel from research reactors was designed by a tri-national team and a half-scale model for MTR fuel constructed in Argentina and tested in Brazil. Two test campaigns have been carried out so far, covering both normal conditions of transportation and hypothetical accident conditions.
    [Show full text]