Ultra High Temperature Reactor Critical Experiment (Ucx) Safety Analysis Report
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WASH-1097.Pdf
WASH 1097 UC-80 THE USE OF THORIUM IN NUCLEAR POWER REACTORS JUNE 1969 PREPARED BY Brookhaven National Laboratory AND THE Division of Reactor Development and Technology WITH THE ASSISTANCE OF ARGONNE NATIONAL LABORATORY BABCOCK & WILCOX GULF GENERAL ATOMIC OAK RIDGE NATIONAL LABORATORY PACIFIC NORTHWEST LABORATORY For sale by the Superintendent of Documents, U.S. Government Printing Office Washington, D.C. 20402 - Price $1.25 FOREWORD This report on "The Use of Thorium in Nuclear Power Reactors" was prepared under the direction of the Division of Reactor Development and Technology, U.S.A.E.C., as part of an overall assessment of the Civilian Nuclear Power Program initiated in response to a request in 1966 by the Joint Committee on Atomic Energy. It represents the results of the inquiry by the Thorium Systems Task Force whose membership included representatives of Babcock & Wilcox Company, Gulf General Atomic Company, the Argonne National Laboratory, the Brookhaven National Laboratory, the Oak Ridge National Laboratory, the Pacific Northwest Laboratory, and the U.S. Atomic Energy Commission. Publication of this report, which provides information basic to the AEC reactor development program, completes one phase of the evaluation effort outlined in the 1967 Supplement to the 1962 Report to the President on Civilian Nuclear Power, issued in February 1967. The 1967 Supplement outlined changes since 1962 in the technical, economic and resource picture and provided background for further study. Specifically, this report represents the consensus of the task force on the potential use of the thorium cycle and the specific thorium fueled reactor designs which have been proposed. -
Eighth World Conference on Nondestructive Testing Huitieme Conference Moiudiale Sur Les Essais Non Destructifs
./ 1ÍOIS_ UJ._ EIGHTH WORLD CONFERENCE ON NONDESTRUCTIVE TESTING HUITIEME CONFERENCE MOIUDIALE SUR LES ESSAIS NON DESTRUCTIFS A NONDESTRUCTIVE EXAMINATION PROGRAM FOR UNCLAD CARBON-COMPOSITE REACTOR FUEL ELEMENTS UN PROGRAMME D'KSSAIS NON DESTRUCTIFS POUR LES ELEMENTS COMBUSTIBLES DE REACTEUR NON GAINÊS EN COMPOSITE DU CARBONE FULLBRIGHT H. J. LOS ALAMOS, NEW MEXICO LOS ALAMOS SCIENTIFIC LABORATORY U. S. A. SUMMARY- ^ non<lestructive testing program for the examination of (U,Zr)C—C reactor fuel elements is described. RESUME :O n décrit un programme d'essais non destructifs pour examiner les elements combustibles de réacteur en (U.Zr)C-C. I. INTRODUCTION The Los Alamos Scientific Laboratory has been active for the past twenty years in the development and testing of graphitic-based high temperature reactor fuel elements. The initial involvement was in the field of nuclear propulsion systems. Project Rover began as a program to develop a nuclear-powered, hydrogen-propelled rocket engine. The target exhaust temperature of the propellant was about 2775 K. The fuel element for such an engine would have to maintain its integrity and strength at higher temperatures and would have to resist currosion by the hot hydrogen gas, which is very reactive. These constraints limited the choice of materials to a very few. Carbon melts above about 3800 K, has excellent high-tenperature strength, and is not a strong neutron absorber. It is very reactive to high temperature hydrogen. The basic fuel element foi the Rover Program became uranium-loaded graphite. The enriched uranium fuel was incorporated into the graphite matrix as uranium oxide, later as py- rolytic-carbon coated uranium dicarbide inicrospheres, and, aosf recently, as a solid solution of uranium carbide and zirconium carbide. -
Quantities of Fissile Materials in US and Soviet
Quantities of Fissile Materials in --US and Soviet ~uclearWeapons Arsenals * Frank von Hippel David H. ~lbri~ht+ Barbara G. Levi PU/CEES Report No. 168 July 1986 * Also Woodrow Wilson School of Public and International Affairs, Princeton University . + Also Federation of American Scientists, 307 Massachusetts Ave. N.E., Washington, DC 20002. Center for Energy and Environmental Studies The Engineering Quadrangle Princeton University Princeton, NJ 08544 TABLE OF CONTENTS a I. INTRODUCTION 11. US STOCKPILE OF WEAPON-GRADE URANIUM 111. US STOCKPILE OF WEAPON-GRADE PLUTONIUM a IV. DISPOSITION OF THE US GOVERNMENT'S STOCKPILE OF NATURAL URANIUM V. SOVIET STOCKPILE OF PLUTONIUM I. INTRODUCTION --TABLE OF CONTENTS History of the Proposal to Cut Off the Production of Fissile Material for Nuclear Weapons a The Verifiability of a Fissile Cutoff The Importance of Knowing the Amounts of Fissile Materials Already in the Nuclear Arsenals 2 REFERENCES Table 1-1. The Amounts of Fissile Material in the US Weapons Stockpile and An Upper-Bound Estimate of the Amount of Separated Plutonium in the USSR I. INTRODUCTION History of the Proposal to Cut Off the Production -of Fissile Material for Nuclear Weapons Although the original nuclear weapons control proposals such as the 1946 Baruch Plan - focused on the control of nuclear weapons materials, recent arms control negotiations have focused principally on the control of long-range nuclear weapons delivery systems. This has been in part due to the shift in the focus of the nuclear arms race from the quantitative to the qualitative. In part also it resulted from the Soviet Union's reluctance to allow intrusive verification arrangements. -
Nuclear Fuels and Reprocessing Technologies: a US Perspective
INL/EXT-20-59106 Review – Nuclear Fuels and Reprocessing Technologies: A U.S. Perspective March 2021 Guy Fredrickson Tae-Sic Yoo DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed 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. References 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 U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof. INL/EXT-20-59106 Review – Nuclear Fuels and Reprocessing Technologies: A U.S. Perspective Guy Fredrickson Tae-Sic Yoo March 2021 Idaho National Laboratory Pyrochemistry & Molten Salt Systems Department Idaho Falls, Idaho 83415 http://www.inl.gov Prepared for the U.S. Department of Energy Office of Nuclear Energy Under DOE Idaho Operations Office Contract DE-AC07-05ID14517 Page intentionally left blank ABSTRACT Reprocessing and/or waste management issues are of concern to the “back end” of the nuclear fuel cycle. Of course, there are a great many “nuclear fuel cycle” scenarios to consider; if not in practice, then at least in theory. The simplest conceptually is the “once through” fuel cycle in which the spent fuel is discarded. -
NRC Collection of Abbreviations
I Nuclear Regulatory Commission c ElLc LI El LIL El, EEELIILE El ClV. El El, El1 ....... I -4 PI AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources: 1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2. The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 3. The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica- tions, it is not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu- ments and correspondence. The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro- ceedings, international agreement reports, grantee reports, and NRC booklets and bro- chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula- tions, and Nuclear Regulatory Commission Issuances. Documents available from the National Technical Information Service Include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. -
Pacific Northwest National Laboratory Operated by Battelle for the U.S
PNNL-11510 UC-2050 Pacific Northwest National Laboratory Operated by Battelle for the U.S. Department of Energy U.S. Graphite Reactor D&D Experience APR 14 1997 OSTI S.M.K. Garrett N. C. Williams February 1997 "0 Z Z T Prepared for the U.S. Department of Energy under Contract DE-AC06-76RLO1830 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor Battelle Memorial Institute, 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 United States Government or any agency thereof, or Battelle Memorial Institute. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. PACIFIC NORTHWEST LABORATORY operated by BATTELLE MEMORIAL INSTITUTE for the UNITED STATES DEPARTMENT OF ENERGY under Contract DE-AC06-76RLO 1830 ' This document was printed on recycled paper. PNNL-11510 UC-2050 U.S. Graphite Reactor D&D Experience S.M.K. Garrett N. C. Williams DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. -
Restricted Data Declassification Decisions 1946 to the Present (RDD 8)
OFFICIAL USE ONLY RESTRICTED DATA DECLASSIFICATION DECISIONS 1946 TO THE PRESENT (RDD-8) January 1, 2002 U.S. Department of Energy Office of Health, Safety and Security Office of Classification Contains information which may be exempt from public release under the Freedom of Information Act (5 U.S.C. 552), exemption number(s) 2. Approval by the Department of Energy prior to public release is required. Reviewed by: Richard J. Lyons Date: 3/20/2002 NOTICE This document provides historical perspective on the sequence of declassification actions performed by the Department of Energy and its predecessor agencies. It is meant to convey the amount and types of information declassified over the years. Although the language of the original declassification authorities is cited verbatim as much as possible to preserve the historical intent of the declassification, THIS DOCUMENT IS NOT TO BE USED AS THE BASIS FOR DECLASSIFYING DOCUMENTS AND MATERIALS without specific authorization from the Director, Information Classification and Control Policy. Classification guides designed for that specific purpose must be used. OFFICIAL USE ONLY OFFICIAL USE ONLY This page intentionally left blank OFFICIAL USE ONLY OFFICIAL USE ONLY FOREWORD This document supersedes Restricted Data Declassification Decisions - 1946 To The Present (RDD-7), January 1, 2001. This is the eighth edition of a document first published in June 1994. This latest edition includes editorial corrections to RDD-7, all declassification actions that have been made since the January 1, 2001, publication date of RDD-7 and any additional declassification actions which were subsequently discovered or confirmed. Note that the terms “declassification” or “declassification action,” as used in this document, refer to changes in classification policy which result in a specific fact or concept that was classified in the past being now unclassified. -
Porosity Effect in the Core Thermal Hydraulics for Ultra High Temperature Gas-Cooled Reactor
Porosity Effect in the Core Thermal Hydraulics for Ultra High Temperature Gas-cooled Reactor Motoo FUMIZAWA Department of Mechanical Systems Engineering, Shonan Institute of Technology 1-1-25 Tsujido-Nishikaigan, Fujisawa, Kanagawa 251-8511 Japan Yoshihiko KANEKO Department of Energy Science and Nuclear Engineering, Musashi Institute of Technology, Japan Masanori IZUMI Japan Atomic Energy Agency, Japan Abstract ∆Tsl(z): temperature difference between fuel matrix surface and fuel element surface; (oC) This study presents an experimental method of porosity evaluation and a predictive thermal-hydraulic analysis with packed spheres in a nuclear reactor core. The porosity 1. Introduction experiments were carried out in both a fully shaken state with the closest possible packing and in a state of non-vibration. The Nowadays, the very high temperature gas-cooled reactor predictive analysis considering the fixed porosity value was projects, or so called GIF (Generation IV International Forum), applied as a design condition for an Ultra High Temperature is energetically developing design studies to establish 1,000 oC Reactor Experiment (UHTREX). The thermal-hydraulic as a coolant outlet temperature and to realize hydrogen computer code was developed and identified as PEBTEMP. production [1-2]. Over an extended period, a fundamental The highest outlet coolant temperature of 1316 oC was design studies have been carried out in the field of high achieved in the case of an UHTREX at Los Alamos Scientific temperature gas-cooled reactors, or HTGR’s [3-8], which show Laboratory, which was a small scale UHTR. In the present that the coolant outlet temperature was around 900 oC. Interest study, the fuel was changed to a pebble type, a porous media. -
Hydrogen Production Using Nuclear Energy No
IAEA Nuclear Energy Series IAEA Nuclear No. NP-T-4.2No. Energy Hydrogen Production Using Nuclear IAEA Nuclear Energy Series No. NP-T-4.2 Basic Hydrogen Production Principles Using Nuclear Energy Objectives Guides Technical Reports INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA ISBN 978–92–0–135110–4 ISSN 1995–7807 IAEA NUCLEAR ENERGY SERIES PUBLICATIONS STRUCTURE OF THE IAEA NUCLEAR ENERGY SERIES Under the terms of Articles III.A and VIII.C of its Statute, the IAEA is authorized to foster the exchange of scientific and technical information on the peaceful uses of atomic energy. The publications in the IAEA Nuclear Energy Series provide information in the areas of nuclear power, nuclear fuel cycle, radioactive waste management and decommissioning, and on general issues that are relevant to all of the above mentioned areas. The structure of the IAEA Nuclear Energy Series comprises three levels: 1 — Basic Principles and Objectives; 2 — Guides; and 3 — Technical Reports. The Nuclear Energy Basic Principles publication describes the rationale and vision for the peaceful uses of nuclear energy. Nuclear Energy Series Objectives publications explain the expectations to be met in various areas at different stages of implementation. Nuclear Energy Series Guides provide high level guidance on how to achieve the objectives related to the various topics and areas involving the peaceful uses of nuclear energy. Nuclear Energy Series Technical Reports provide additional, more detailed, information on activities related to the various areas dealt with in the IAEA Nuclear Energy Series. The IAEA Nuclear Energy Series publications are coded as follows: NG — general; NP — nuclear power; NF — nuclear fuel; NW — radioactive waste management and decommissioning. -
The Times They Were a Changin'
the Agnew Years The Times They Were a Changin’ regain the initiative in weapons development that we’d lost to Livermore. In 1970 this Laboratory was still largely a weapons lab, but Livermore was doing a better. more aggressive selling job and was pushing for the enhanced radiation weapons and all the strategic weapons—the nuclear warheads for Minuteman and Polaris. Their reputation was better than ours, or at least perceived to be so by some people. Harold’s vision was to restore the luster that Los Alamos had lost. It’s true that he thought the Laboratory was premier in all fields and he would undertake anything, but above all he wanted to be first in our principal mission of weapons develop- ment, SCHREIBER: There’s another aspect to the Bradbury-Agnew transition that I feel is also important to recognize, At the end of World War 11, when Norris became Director, a lot of people who had served during the war years on Laboratory advisory boards simply disappeared. Norris really didn’t have an Raemer Schreiber (left) joined the Laboratory in 1943. In the ’50s he was the Leader existing management structure to work with, of the Weapons and the Nuclear Propulsion divisions and then, in 1961, was so he was able to start with a clean slate. appointed Technical Associate Director. He remained in that position after Agnew Twenty-five years later the Laboratory was became Director until “Harold, in 1972, decided I was really Deputy Director, so he firmly established, and Norris was working changed my title. -
Massoud T. Simnad Papers
http://oac.cdlib.org/findaid/ark:/13030/kt467nf3ms No online items Massoud T. Simnad Papers Special Collections & Archives, UC San Diego Special Collections & Archives, UC San Diego Copyright 2011 9500 Gilman Drive La Jolla 92093-0175 [email protected] URL: http://libraries.ucsd.edu/collections/sca/index.html Massoud T. Simnad Papers MSS 0577 1 Descriptive Summary Languages: English Contributing Institution: Special Collections & Archives, UC San Diego 9500 Gilman Drive La Jolla 92093-0175 Title: Massoud T. Simnad Papers Identifier/Call Number: MSS 0577 Physical Description: 8 Linear feet(20 archive boxes and 2 oversize folders) Date (inclusive): 1960-2002 Abstract: Papers of Massoud T. Simnad (1921-2002), an engineer in nuclear energy and UCSD adjunct professor of materials science and engineering. The collection documents Simnad's work in the field of nuclear reactor technologies and superconductivity and contains files related to his research, consulting, journal articles, grant proposals, and conference papers. Acquisition Information Acquired 2002. Preferred Citation Massoud T. Simnad Papers, MSS 577. Special Collections & Archives, UC San Diego. Biography Massoud T. Simnad was born in Iran in 1921 and grew up in Istanbul. At the age of 15, he left Istanbul for London where he studied mining engineering at London University's Imperial College of Science and Technology. He earned his B.S. in 1942 and his Ph.D in 1946 at Cambridge University specializing in materials science. After graduation he accepted a guest fellowship at the Carnegie-Mellon University in Pittsburgh. From 1949, Simnad lived in the U.S. and served as an educator, technical adviser, and consultant to various academic institutions and scientific corporations. -
Nuclear Science and Technology for Ceramics
UNITED STATES DEPARTMENT OF COMMERCE Alexander B. Trowbridge • Acting Secretary NATIONAL BUREAU OF STANDARDS • A. V. Astin, Director Nuclear Science and Technology for Ceramists Proceedings of a Symposium April 7-12, 1966 Held under the auspices of the Ceramic Educational Council of the American Ceramic Society, with the cooperation of the National Bureau of Standards, and under the sponsorship of the Office of Naval Research. The symposium took place at the 68th Annual Meeting of the American Ceramic Society in Washington, D.C. National Bureau of Standards Miscellaneous Publication 285 Issued May 26, 1967 For sale by the Superintendent of Documents, U.S. Government Printing Office, Washington, D.C. 20402 - Price $1.75 (cloth) Library of Congress Catalog Card Number: 67-60013 Contents Introduction 1. Material Radiation Environment Carl 0. Muehlhause National Bureau of Standards Washington, D. C. 2. Radiation Damage in Ceramics Alan B. Lidiard United Kingdom Atomic Energy Research Establishment Harwell, Didcot, Berkshire, England 3. Physical Properties of Irradiated Ceramic Materials Paul W. Levy Brookhaven National Laboratory Upton, L. I., New York 4. Chemical Problems Associated with Lattice Defects R. J. Thorn and G. H. Winslow Argonne National Laboratory Argonne, Illinois 5. Nuclear Fuel Materials D. W. Readey and J. H. Handwerk Argonne National Laboratory Argonne, Illinois 6. Reactor Materials Design Don R. deHalas, W. D. Freshley and W. C. Morgan Pacific Northwest Laboratories Battelle Memorial Institute Richland, Washington Introduction Our rapidly advancing technology continually presents demands to the materials scientist and engineer to make present materials do new things or to devise new materials. To meet these ever- expanding challenges, the ceramist must be able to bring to bear in his field the most advanced and sophisticated ideas and techniques available from other fields.