Experimental Needs in Criticality Safety
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Criticality Safety in Processing Plants
Chapter V CRITICALITY SAFETY IN PROCESSING PLANTS A. Plant Features with Criticality Potential Processing plants contain a multiplicity of work stations, and areas for both long-term and short-term storage. Criticality safety considerations go beyond the analysis of each of these in terms of subcritical individual units or storage arrays. The progression of fissile material through a plant involves transfers and special handling during which unusual conditions may be encountered. It is important that these operations be governed by procedures and be carried out by well-trained personnel. Consider a plant for processing highly enriched uranium as solids, such as fabrication of weapon components or fuel elements for reactors. It is essential to avoid the effect of massive fissile units falling together or encountering other units as the result of an accident with transfer equipment. Minimum spacing between units can be maintained by the use of birdcages, provided there are appropriate procedures for loading and unloading them. In a plant for scrap recovery or processing irradiated fuel, the operations involving fissile solutions must be carefully planned. It is noteworthy that all criticality accidents that have occurred in processing plants have involved solutions. Mishaps that have led to these accidents include solution leakage, precipitation, dissolution of solids, instrument failure, and transfer among vessels. Avoidance of these mishaps calls for continued cooperation of criticality safety and operating personnel. In general, both physical and administrative criticality safety practices must be tailored to specific plant conditions. This requirement inevitably will require judgment. Special evaluation also may be required because there is no “standard” plant for which universal criticality safety recipes can be defined. -
CRITICALITY SAFETY in the HANDLING of FISSILE MATERIAL the Following States Are Members of the International Atomic Energy Agency
IAEA Safety Standards Safety through international standards for protecting people and the environment “Governments, regulatory bodies and operators everywhere must ensure that nuclear material and radiation sources are used Standards Series No. SSG-27 Safety IAEA beneficially, safely and ethically. The IAEA safety standards are Criticality Safety in the designed to facilitate this, and I encourage all Member States to make use of them.” Handling of Yukiya Amano Director General Fissile Material Specific Safety Guide No. SSG-27 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA ISBN 978–92 –0–140010–9 ISSN 1020–525X 13-36371_PUB1594_cover.indd 1-3 2014-05-09 07:41:01 RELATED PUBLICATIONS IAEA SAFETY STANDARDS AND RELATED PUBLICATIONS FUNDAMENTAL SAFETY PRINCIPLES IAEA Safety Standards Series No. SF-1 IAEA SAFETY STANDARDS STI/PUB/1273 (37 pp.; 2006) Under the terms of Article III of its Statute, the IAEA is authorized to establish or adopt ISBN 92–0–110706–4 Price: €25.00 standards of safety for protection of health and minimization of danger to life and property, and to provide for the application of these standards. GOVERNMENTAL, LEGAL AND REGULATORY FRAMEWORK The publications by means of which the IAEA establishes standards are issued in the FOR SAFETY IAEA Safety Standards Series. This series covers nuclear safety, radiation safety, transport IAEA Safety Standards Series No. GSR Part 1 safety and waste safety. The publication categories in the series are Safety Fundamentals, STI/PUB/1465 (63 pp.; 2010) Safety Requirements and Safety Guides. ISBN 978–92–0–106410–3 Price: €45.00 Information on the IAEA’s safety standards programme is available on the IAEA Internet THE MANAGEMENT SYSTEM FOR FACILITIES AND ACTIVITIES site IAEA Safety Standards Series No. -
Critical Assemblies: Dragon Burst Assembly & Solution Assemblies
Submitted to ANS/NT (2021). LA-UR-21-20906 DRAFT Critical Assemblies: Dragon Burst Assembly & Solution Assemblies Robert Kimpland, Travis Grove, Peter Jaegers, Richard Malenfant, and William Myers* Los Alamos National Laboratory Los Alamos, NM 87545 Abstract: This work reviewed the historical literature associated with the Dragon experiment and Water Boiler reactors operated at Los Alamos during the Manhattan Project. Frisch’s invited talk given at the Fast Burst Reactor Conference held the University of New Mexico in Albuquerque, NM in 1969 is quoted. From the literature review, basic models for the Dragon experiment and for a Water Boiler type assembly (aqueous homogeneous reactor) were created that can be used for conducting multi-physics simulations for criticality excursion studies. This methodology utilizes the coupled neutronic-hydrodynamic method to perform a time-dependent dynamic simulation of a criticality excursion. MCNP® was utilized to calculate important nuclear kinetic parameters that were incorporated into the models. Simulation results compared reasonably well with historic data. Keywords: Manhattan Project; Dragon Experiment; Water Boiler Reactors; Multiphysics Simulation; Coupled Neutronic-Hydrodynamic Method. theoretical models. The experimenters gained a wealth of Introduction data and experience on reactor operations that still form Lise Meitner and her nephew, Otto Frisch, discovered the basis of nuclear operations practiced today. nuclear fission and named it such in a February 1939 issue of Nature. Physicists throughout the world immediately History and Design Description of the Dragon realized that the emission of 2-3 neutrons from the Assembly process could lead to a chain reaction and the release of a In October 1944, Otto R. -
LOS ALAMOS SCIENTIFIC LABORATORY of the University of California LOS ALAMOS ● NEW MEXICO
LOS ALAMOS SCIENTIFIC LABORATORY of the University of California LOS ALAMOS ● NEW MEXICO A Review of Criticality Accidents DO NOT CIRCULATE _.>-. —J..-.=-_ ri-- PERMANENT RETENTION E > .;. l!E- ..* m I F “-.— ..’- li==-*-” .. L UNITED STATES ATOMIC ENERGY COMMISSION I CONTRACT W-7405 -ENG. 36 a ., r b :., LEGAL NOTICE This report was prepared as an account of Government sponsored work. Neither the United States, nor the Commission, nor any pereon acting on behalf of the Commission: A. Makes any warranty or representation, expressed or implied, with respect to the accu- racy, completeness, or usefulness of the information contained in this report, or that the use of any Information, apparatua, method, or process disclosed in this report may not infringe privately owned rights; or B. Assumes any liabilities with respect to the use of, or for damagea resulting from the use of any information, apparatus, method, or process disclosed in this report. As used in the above, “person acting on behalf of the Commission” includes anY em- ployee or contractor of the Commission, or employee of such contractor, @ the extent that such employee or contractor of the Commission, or employee of such contractor prepares, disseminates, or provides acceas to, any information pursuant to hts employment or cootract with the Commission, or his employment with such contractor. This reportexpressesthe opinionsof the authoror authorsand doesnot necessarilyreflecttheopinions or views of the Los Alamos ScientificLaboratory. 1 4 . 1’ LA-3611 UC-46, CRITICALITY STUDIES TID-4500 LOS ALAMOS SCIENTIFIC LABORATORY of the University of California LOS ALAMOS c NEW MEXICO Reportwritten:January 1967 Reportdistributed:September26,1967 A Review of Criticality Accidents by William R. -
Criticality Safety
Criticality Safety Qualification Standard Reference Guide APRIL 2011 This page is intentionally blank. Table of Contents FIGURES ...................................................................................................................................... iii PURPOSE ...................................................................................................................................... 1 SCOPE ........................................................................................................................................... 1 PREFACE ...................................................................................................................................... 1 ACKNOWLEDGEMENTS ......................................................................................................... 2 TECHNICAL COMPETENCIES ............................................................................................... 3 1. Criticality safety personnel must demonstrate a working level knowledge of the fission process....................................................................................................................................... 3 2. Criticality safety personnel must demonstrate a working level knowledge of the various types of radiation interaction with matter. ................................................................................ 9 3. Criticality safety personnel must demonstrate a working level knowledge of criticality control and safety parameters. ............................................................................................... -
Consideration of Criticality When Directly Disposing Highly Enriched Spent Nuclear Fuel in Unsaturated Tuff: Bounding Estimates
SANDIA REPORT SAND96-0866 • UC-900 Unlimited Release f\. - ' \z \J Printed May 1996 .,.„ ~ g <;v,? OST1 Consideration of Criticality when Directly Disposing Highly Enriched Spent Nuclear Fuel in Unsaturated Tuff: Bounding Estimates Rob P. Rechard, Martin S. Tlerney, Larry C. Sanchez, Mary-Alena Martell Prepared by Sandia National Laboratories Albuquerque, New Mexico 87185 and Livermore, California 94550 for the United States Department of Energy under Contract DE-AC04-94AL85000 Approved for public release; distribution is unlimited. SF2900Q(8-81) Issued by Sandia National Laboratories, operated for the United States Department of Energy by Sandia Corporation. NOTICE: This report was prepared as an account of work sponsored by an agency of the United States Government Neither the United States Govern• ment nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, prod• uct, or process disclosed, or represents that its use would not infringe pri• vately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government, any agency thereof or any of their contractors or subcontractors. The views and opinions expressed herein do not necessarily state or reflect those of the United States Govern• ment, any agency thereof or any of their contractors. Printed in the United States of America. This report has been reproduced directly from the best available copy. -
A Technical Retrospective of the Former South African Nuclear Weapon Programme Robert E
SIPRI A TECHNICAL Policy Paper RETROSPECTIVE OF THE FORMER SOUTH AFRICAN NUCLEAR WEAPON PROGRAMME ROBERT E. KELLEY October 2020 STOCKHOLM INTERNATIONAL PEACE RESEARCH INSTITUTE SIPRI is an independent international institute dedicated to research into conflict, armaments, arms control and disarmament. Established in 1966, SIPRI provides data, analysis and recommendations, based on open sources, to policymakers, researchers, media and the interested public. The Governing Board is not responsible for the views expressed in the publications of the Institute. GOVERNING BOARD Ambassador Jan Eliasson, Chair (Sweden) Dr Vladimir Baranovsky (Russia) Espen Barth Eide (Norway) Jean-Marie Guéhenno (France) Dr Radha Kumar (India) Ambassador Ramtane Lamamra (Algeria) Dr Patricia Lewis (Ireland/United Kingdom) Dr Jessica Tuchman Mathews (United States) DIRECTOR Dan Smith (United Kingdom) Signalistgatan 9 SE-169 72 Solna, Sweden Telephone: + 46 8 655 9700 Email: [email protected] Internet: www.sipri.org A Technical Retrospective of the Former South African Nuclear Weapon Programme robert e. kelley October 2020 Contents Preface v Acknowledgements vi Abbreviations vii Summary ix 1. Introduction 1 A brief history of the South African nuclear weapon programme 3 Political statement of the programme 5 The end of the programme 5 IAEA transparency visits in 1993 6 Box 1.1. The records of the International Atomic Energy Agency visits 2 to South Africa in 1993 Box 1.2. Special limitations on inspectors 8 2. The Somchem plant 9 Shaped charge development 11 Enrichment support at Somchem 13 Box 2.1. Gun-type weapons 10 3. The Vastrap nuclear test site 15 Box 3.1. A possible nuclear test in the South Atlantic 16 4. -
LA-13638, "A Review of Criticality Accidents"
LA-13638 Approved for public release; distribution is unlimited. A Review of Criticality Accidents 2000 Revision ENERGY POWER TIME Los Alamos NATIONAL LABORATORY Los Alamos, New Mexico 87545 Los Alamos National Laboratory is operated by the University of California for the United States Department of Energy under contract W-7405-ENG-36. Printing coordination by Jerry Halladay and Guadalupe Archuleta, Group CIC-9 Photocomposition by Wendy Burditt, Group CIC-1 Cover Design by Kelly Parker, Group CIC-1 Cover Illustration: Power and energy traces representative of a typical criticality excursion in solution - from the SILENE experimental report, reference # 4. An Affirmative Action/Equal Opportunity Employer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither The Regents of the University of California, the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by The Regents of the University of California, the United States Government, or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of The Regents of the University of California, the United States Government, or any agency thereof.Los Alamos National Laboratory strongly supports academic freedom and a researcherÕs right to publish; as an institution, however, the Laboratory oesd not endorse the viewpoint of a publication or guarantee its technical correctness.