DOCSLIB.ORG

"Handbook of Acronyms & Initialisms."

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
NUREG-0544 A HANDBOOK OF ACRONYMS AND INITIALISMS p* "muq % 5 ..... Office of Administration U. S. Nuclear Regulatory Commission '9 05 140 f73 NUREG4544 A HANDBOOK OF ACRONYMS AND INITIALISMS Manuscript Completed: March 1979 Date Published: March 1979 Division of Technical Information and Document Control Office of Administration U. S. Nuclear Regulatory Commission Washington, D.C. 20555 PREFACE This " Handbook of Acronyms and Initialisms" is a dictionary of acro- nyms, initialisms and similar condensed forms observed in use in the nuclear industry. It was compiled to serve as a source for learning the meaning of undefined acronyms found in the literature. The use of these acronyms in NRC documents is neither recommended or condemned, and, similarly, the accuracy and completeness of this document is not assured. If you use these or similar condensed forms in your writing we strongly recommend the practice of writing out the condensed form first and following it with the acronym or initialism in parentheses; for example, U.S. Nuclear Regulatory Commission (NRC). After the ini- tial writing out of the full name, the acronym may be used by itself. For the purposes of this document the following definitions apply: Acronym - a pronounceable term formed from the initial letters of a compound expression, e.g. NASA (National Aeronautics andSpaceAdministration)orRem({oentgen[quivalent man). Initialism - a term, not pronounceable, formed from the initial letters of a compound expression, e.g. CIA (Central Intelligence Agency) or ac (alternating current). Comments, criticisms or suggestions regarding this publication are en- couraged. In so far as possible, we would like this document to be a valuable part of your reference material. Revisions will be published periodically as needed. iii A A HANDBOOK 0F ACRONYMS AND INITIALISMS AlW Large ship reactor prototype A-57 AMF 100 kw(th) Reactor, dismantled and reconstructed as HOR in Delft, Netherlands AA Access authorization AACC American Association for Contamination Control AAEC Australian Atomic Energy Commission AAPM American Association of Physicists in Medicine 22 AARR Argonne Advanced Research Reactor (see also A R ) AASHO American Association of State Highway Officials ABCC Atomic Bomb Casualty Commission (AEC) ABFS Auxiliary building filter system ABLE Activity balance line evaluation AC Advisory Committee A/C Air conditioning ac Alternating current ACAD Air containment atmosphere dilution ACB Air (operated) circuit breaker ACDA Arms Control and Disarmament Agency ACHP Advisory Council on Historic Preservation ACI American Concrete Institute ACLP Above core load pad (fuel assembly) ACPDS Advisory Committee on Personal Dosimetry Services (NSF) -g- ACPR Advanced core performance reactor ACPR Annular core pulse reactor ACRS Advisory Committee on Reactor Safeguards ACS American Chemical Society ACS Auxiliary cooling system ADDS Applied digital data systems ADEA Association belge pour le Developpement Pacifique de l'Energie Atomique (Belgian Association for the Peaceful Development of Atomic Energy) ADP Automatic data processing ADR Audit discrepancy report ADS Automatic depressurization system ADU Ammonium diuranate AE Architect-engineer AE Acoustic emission AE-6 (WBNS) Water boiler neutron source, (North American Aviation) Santa Susanna, California AEA Atomic Energy Authority of the United Kingdom, London AEB Auxiliary equipment building AEC U.S. Atomic Energy Commission AECL Atomic Energy of Canada Ltd. AECM Atomic Energy Commission manual AECPR AEC procurement regulations AERE Atomic Energy Research Establishment, United Kingdom AES-1 Power reactor at Obninsk, USSR -3- AETR Advanced Epithermal Thorium Reactor built by Atomics International (AI) for Southwest Atomic Energy Associates (SAEA) AETR Advanced Engineering Test Reactor, Idaho Falls, Idaho AETRA Cross section reactor physics computer code AFBMA Anti-Friction Bearing Manufacturers Association AF NETF Air Force Nuclear Engineering Test Facility AFRRI Armed Forces Radiobiology Research Institute AFSR Argonne Fast Source Reactor, NRTS, 1 kw(th) AGC Aerojet General Corporation AGMA American Gear Manufacturing Association AGN Teaching reactor built by Aerojet-General Nucleonics AGN-201-100 U.S. Naval Postgraduate School AGN-201 Reactor, Monterey, California (Aerojet-General Nucleonics, builder and designer) AGR Advanced gas-cooled reactor AGS Alternating Gradient Synchrotron, BNL AGS Annulus gas system AGU American Geophysical Union AGZ Actual ground zero AHR Aqueous homogeneous reactor AHFR-1 Argonne High Flux Reactor, ANL AI Atomics International AICE American Institute of Chemical Engineers AIF Atomic Industrial Forum -4- AIGS Auxiliary inerting gas subsystem AIPA American Industrial Hygiene Association AIHX Auxiliary intermediate heat exchanger AII-V Autorat#c Industries, Inc. , Vitro Engineering AIMME American Institute of Mining and Metallurgical Engineers AINSE Australian Institute of Nuclear Science and Engineering AIP Approval in principle AIREK-ll Group and feedback kinetics reactor computer code AISC American Institute of Steel Construction AISE Association of Iron and Steel Engineers AISI American Iron and Steel Institute AITS Action item tracking system AKK Atomkraftkonsortiet Krangede Ad & Co., nuclear power study group, Stockholm, Sweden AKS Nuclear power plant planning association, Baden-Wuerttemberg, Germany AKV AKB Atomkraftwerk, Simpevarp, Sweden (proposed power reactor,170 MW(th)) AL Analytical limits AL Action (indicator) level-, those radiological doses and concentrations at which actions should be taken ALAP As low as practical ALARA As low as reasonably achievable ALCP Area local control panel ALECTO Homogeneous Research Reactor Zero Power, CEA, Saclay, France -5- , ALICE Fusion research device at Lawrence Radiation Laboratory ALIP Annular linear induction pump ALIZE-II Tank reactor at Saclay, France ALKEM Alphachemie und Metallurgie, Gmbh., plutonium fabricators, West Germany ALMS Auxiliary liquid metal system ALP Assembly language preprocessor ALPHA Fusion device, Leningrad, USSR ALPHGR Average linear planar heat generation rate ALPR Argonne Low Power Reactor, redesignated SL-1, NRTS, Idaho power reactor, 3 MW(th) (now dismantled) ALRR Ames Laboratory Research Reactor, Ames, Iowa 5 mw(th) ALSI Aluminum silicon alloy u' sed in slug canning process at Hanford AM-1 First USSR power reactor, 5 MW(e), Obninsk, USSR AMAD Activity median aerodynamic diameter AMB-1, 2 - 1 Power reactor, BWR, superheated, 300 MW(th), 100 MW(e), Beloyarsk, USSR AMB-1, 2 - 2 Proposed power reactor, BWR with superheat, 200 MW(e), Beloyarsk, USSR AMCF Alkali metal cleaning facility AMCo Aerojet Manufacturing Company A.M.P.E.R.E. Atomes et Molecules par Etudes Radio-Electriques, c/o M. C. Bene, Institut de Physique, Geneva, Switzerland A/N Alpha numeric A/N As needed -6- ANC Aerojet Nuclear Corporation ANIM Association of Nuclear Instrument Manufacturers ANL Argos. > National Laboratory ANR Association of Neutron Radiographers ANS American Nuclear Society ANSCAT Scattering angle reactor physics computer code ANSI American National Standards Institute A0 Abnormal occurrence A0G Augmented off gas system A0I Advance ordering information AP Access permit; Access permittee AP Associated Press APA Administrative Procedures Act APC Argon purge cart APCA Air Pollution Control Association APCEF Advancad Power Conversion Experimental Facility, U.S. Army gas-cooled reactor systems development, Ft. Belvoir, Virginia APDA Atomic Power Development Associetes APDMS Axial power distribution monitoring systems APHA American Public Health Association API American Petroleum Institute APL Applied Physics Laboratory (University of Chicago) APL A programming language -7- APL Authorized possession limits APPA American Public Power Association APR Advance Production Release (LLL) APR Automatic pressure relief APRM Average power range monitor APS American Physics Society APS-1 Power reactor, 30MW(th), Obninsk, USSR APSR Axial power shaping rods APTR Advanced Pressure Tube Reactor, heterogeneous, enriched uranium, water moderated, USA APU Auxi'iary power unit AQUILLON Heavy water research reactor, CEA, Saclay, France 22 AR Argonne Advanced Research Reactor (see also AARR) ARBOR Argonne Boiling Water Reactor, NRTS ARBUS Power reactor, organic-cooled and -moderated, 5 MW(th), 0.75 MW(e), New Melekess, USSR ARDA Atomic Research and Development Authority, State of New Yc-k AREA American Railway Engineering Association AREA Army reactor area Argonaut Argonne nuclear assembly for university training, ANL (CP-11) ARHC0 Atlantic Richfield Hanford Company ARM Area radiation monitor ARMF 1 & II Advanced Reactivity Measurement Facility, (NRTS) ARMS Aerial radiological measurements and surveys -8- ARPI Absolute rod position indication ARR Armour Research Foundation Reactor, Chicago, Illinois, 11 KW(th) ARS Advance record system ASADA New York State Atomic and Space Development Authority ASCE American Society of Civil Engineers ASHRAE American Society of Heating, Refrigeration and Air Conditioning Engineers ASLAB Atomic Safety and Licensing Appeal Board ASLAP Atomic Safety and Licensing Appeal Panel ASLB Atomic Safety Licensing Board A S '_B P Atomic Safety and Licensing Board Panel ASM American Society of Metals ASME American Society of Mechanical Engineers ASNT American Society for Nondestructive lesting ASQC American Society for Quality Control ASR Automatic send and receive teletype terminal ASTM American Society of Testing Materials AT Acceptance tag ATC Adiabatic
Load more

Recommended publications
  • Safeguards at Research Reactors: Current Practices, Future Directions
    FEATURES Safeguards at research reactors: Current practices, future directions Some new verification measures are being introduced to improve the efficiency and the effectiveness of the Agency's safeguards by Giancarlo /approximately 180 research reactors and crit- immersed in a large pool of water that provides Zuccaro-Labellarte ical assemblies currently are under IAEA safe- both cooling and neutron moderation. The fuel and guards. The vast majority of the research reac- assemblies in the core of a swimming pool reac- Robert Fagerholm tors operate at relatively low power levels (10 tor are normally visible and accessible for safe- megawatts-thermal or lower) and the critical guards measurements. assemblies at virtually zero power.* From a Other types of research reactors operate at safeguards standpoint, this is important since a higher power levels (exceeding 10 megawatts- reactor's power level is a determining factor of thermal). They need more powerful heat its capability to produce plutonium. Along with removal systems and are therefore normally high-enriched uranium (HEU) and uranium- enclosed in core vessels and equipped with 233, plutonium is considered a "direct use" coolant pumps and heat exchangers. The fuel material which could be diverted for the pro- elements in the reactor core at these installa- duction of nuclear weapons. tions are usually not visible or accessible for In this article, the IAEA's safeguards safeguards measurements. implementation at research reactors is Research reactors are widely used for scien- addressed, including aspects related to diver- tific investigations and various applications. sion and clandestine production scenarios and Neutrons produced by research reactors provide main verification activities.
    [Show full text]
  • 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.
    [Show full text]
  • EMD Uranium (Nuclear Minerals) Committee 2017 EMD Uranium (Nuclear Minerals and REE) Committee Mid-Year Report
    EMD Uranium (Nuclear Minerals) Committee 2017 EMD Uranium (Nuclear Minerals and REE) Committee Mid-Year Report November 26, 2017 Table of Contents Page UCOM Committee Personnel .………………………….... 3 UCOM Committee Activities ……………………………. 4 UCOM Publications and Nuclear Outreach ……………… 5 Objectives of UCOM Reports ……………………………. 7 Executive Summary ……………………………………... 8 Introduction ………………………………………………. 9 Sources of Uranium 13 Energy Subsidies ………………………………………….. 14 Uranium Prices ………………….. ………………………. 17 Industry Response to Uranium Price Fluctuations ……………. 19 The Impact of Japan ………………………………………. 19 Uranium Production in the U.S.- 4th Quarter, 2017 . ……… 20 U.S. Uranium Mill in Production (by State) …………………. 20 U.S. Uranium In-Situ Recovery Plants in Production (by State) 20 Uranium Exploration. ………………………………………. 23 Uranium Mining ……………………………………………. 23 Uranium Milling ……………………………………………. 24 Uranium Conversion ………………………………………. 24 Uranium Enrichment ……………………………………….. 25 Uranium Reconversion and Nuclear Fuel Fabrication . ……. 25 Interim Storage and Final Disposal ………………………… 26 U.S. Nuclear Power Plants Under Construction …………… 30 Design Certifications …………………………………………….. 31 Small Modular Reactors (SMRs) …………………………... 32 Nuclear Waste Storage ……………………………………… 33 International Uranium Exploration & Development ………. 34 International Uranium Production …………………………. 35 International Nuclear Power Activity ……………………… 36 Overall Perspective ………………………………………… 38 Coal vs. Nuclear Power & National Gas ……………………. 38 Renewable Energy vs. Nuclear Power ………………………. 38
    [Show full text]
  • Reed College Reed Research Reactor License No
    REED COLLEGE REED RESEARCH REACTOR LICENSE NO. R-112 DOCKET NO. 50-288 LICENSE RENEWAL APPLICATION SAFETY ANALYSIS REPORT, TECHNICAL SPECIFICATIONS, ENVIRONMENTAL CONSIDERATIONS, AND OPERATOR REQUALIFICATION PROGRAM REDACTED VERSION* SECURITY-RELATED INFORMATION REMOVED *REDACTED TEXT AND FIGURES BLACKED OUR OR DENOTED BY BRACKETS REED COLLEGE __ Portland, Oregon 97202 REACTOR FACILITY August 29, 2007 US Nuclear Regulatory Commission Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Docket: 50-288 Subject: License Renewal This is Reed College's application for a renewal of the operating license for the Reed Research Reactor, License R-1 12, Docket 50-288. Reed College is a private non-profit educational institution incorporated in the State of Oregon. The applicant information is: Reed Institute (dba Reed College) 3203 SE Woodstock Blvd. Portland, OR 97202 Reed is applying to be licensed as a Class 104 facility for an additional 20 years. As part of the relicensing, Reed is upgrading the licensed power level to 500 kW. The license will be used for primarily educational activities in Portland, Oregon and the surrounding region. Enclosed are the supporting documents, including; 1. Updated Safety Analysis Report (SAR) 2. Technical Specifications 3. Financial Qualifications and Decommissioning per 1OCFR50.33(f)(2) and 1OCFR50.33(k) 4. Environmental Report 5. Radiation Protection Plan 6. Operator Requalification Plan• 7. Fire Plan 8. Administrative Procedures There are no changes to Reed College's Emergency Plan or Physical Security Plan being implemented as part of the relicensing, so they are not included in this submittal. The most recent versions of each plan remains in effect.
    [Show full text]
  • Canadian Nuclear Safety Commission
    Canadian Nuclear Safety Commission Performance Report For the period ending March 31, 2007 ________________________ ________________________ The Honourable Gary Lunn Linda J. Keen, M.Sc. Minister President and Chief Executive Officer Natural Resources Canada Canadian Nuclear Safety Commission Table of Contents SECTION I: OVERVIEW........................................................................................................... 1 Message from the President and Chief Executive Officer...................................................................3 Management Representation Statement ...............................................................................................4 Summary Information..................................................................................................................... 5 Mission.................................................................................................................................... 5 Governance ............................................................................................................................. 5 Regulatory Framework ........................................................................................................... 5 Funding of CNSC Operations................................................................................................. 6 Additional Funding Resources Received for 2006-07............................................................ 6 Financial Resources ...............................................................................................................
    [Show full text]
  • Supplementary Information Written Submission from Lake Ontario
    CMD 19-M24.7A Date: 2019-10-30 File / dossier : 6.02.04 Edocs pdf : 6032342 Supplementary Information Renseignements supplémentaires Written submission from Mémoire de Lake Ontario Waterkeeper Lake Ontario Waterkeeper et and Ottawa Riverkeeper Sentinelle Outaouais Regulatory Oversight Report for Rapport de surveillance réglementaire Canadian Nuclear Laboratories des sites des Laboratoires Nucléaires (CNL) sites: 2018 Canadiens (LNC) : 2018 Commission Meeting Réunion de la Commission November 7, 2019 Le 7 novembre 2019 This page was intentionally Cette page a été intentionnellement left blank laissée en blanc Amendments have been made to these submissions to reflect additional information that has been received by Ottawa Riverkeeper and Lake Ontario Waterkeeper since October 7. In addition to some typographical corrections, the following changes were made to these previously submitted main report: 1) Recommendation #20 no longer requires that CNL confirm whether a DFO permit has been issued for any Chalk River facilities. This recommendation still requests that any assessments accompanying the permit application be provided. Now it also requests a timeline for CNSC staff consideration of the permit; 2) Recommendation #21 no longer requires that CNL confirm whether there are any ECAs for the Chalk River site. This recommendation still requests any assessments that were undertaken to determine whether one was necessary; 3) Discussions of issues concerning DFO permits and ECAs on page 20 have been updated to reflect the fact that Ottawa Riverkeeper is no longer waiting for confirmation of whether there are any DFO permits or ECAs for the Chalk River site. However, formal access to information requests are still ongoing to provide more background information on both DFO and ECA assessments, and CNL has still been asked to provide this information as well; and 4) Discussions of the Port Hope Harbour wall collapse on page 26 have been amended to reflect additional disclosures received since October 7.
    [Show full text]
  • Declaration of David Lochbaum
    Critique of the Analysis of Safety and Environmental Risks Posed by Spent Fuel Pool Leaks in the NRC’s Draft Waste Confidence Generic Environmental Impact Statement Declaration of David Lochbaum Under penalty of perjury, I, David Lochbaum, declare as follows: I. INTRODUCTION 1.1 I am the director of the nuclear safety project for the Union of Concerned Scientists (UCS). The UCS puts rigorous, independent science to work to solve our planet's most pressing problems. Joining with citizens across the country, we combine technical analysis and effective advocacy to create innovative, practical solutions for a healthy, safe, and sustainable future. The UCS has over 93,000 members. 1.2 I have been retained by a group of environmental organizations to assist in the preparation of comments invited by the U.S. Nuclear Regulatory Commission (NRC), on its Draft Generic Environmental Impact Statement on the Waste Confidence Decision (WC DGEIS). 1.3 The purpose of my declaration is to address the adequacy of the discussion of spent fuel pool leak risks in the WC DGEIS to support the NRC’s proposed finding in 10 CFR. § 51.23(a)(2) that it is feasible to safely store spent nuclear fuel in spent fuel pools after nuclear power reactors permanently cease operation. 1.4 My declaration is organized as follows: Section II (page 3) discusses my professional qualifications. Section III (page 5) provides introductory material on spent fuel storage in the United States and treatment of spent fuel pool leaks within the WC DGEIS. Section IV (page 10) discusses the NRC’s failure to evaluate experience from past spent fuel pool leaks in assessing future spent fuel pool leak risks for the WC DGEIS.
    [Show full text]
  • Westinghouse Hanford Company Reference Guide Acronyms and Abbreviations
    00 3087 WHC-EP-0009 Volume 1 Westinghouse Hanford Company Reference Guide Acronyms and Abbreviations Prepared for the U.S. Department of Energy Assistant Secretary for Management and Administration ~ Westinghouse \::::) Hanford Company Richland, Washington Hanford Operations and Engineering Contractor for the U.S. Department of Energy under Contract DE-AC06-87RL 10930 Approved for Public Release RECORD OF (1) Document Number I REVISION Page lofl J WHC-EP -0009 J W Title and Abbreviations V-: estinghouse Hanford Company Rl:fe-=r~nce- ~ui-de . Acronyms CHANGE CONTROL RECORD Authorized for Release (3) Rev1s1on (4) Description of Change - Replace, Add. and Delete Pages (5) Cog.1Pro1. Engr. (6) Cog./Pr0J . Mgr. Date (7) Revision 1 Page 7 20 52 100 103 110 258 318 7)0/fc Replace all to show minor mJ. ,-~ X't~ corrections to content ' A-7320-005 (12189) The following is a summary of instructions to be used in preparing Record of Revision page and how appropriate Engineering Change Notice (ECN) and revisions are identified. NOTE: Prior to revision of an engineering document, all proposed changes shall have been approved by an ECN. The Record of Revision sheet shall include the following information. 1) The engineering document number. 2) The title of the engineering document. Change Control Record 3) The revision number of the change. 4) A description of the change, including page changes, additions, and deletions where appropriate. List the approved ECN number(s) which have been incorporated. 5) The authorizing signature of the Cognizant/Project Engineer signifying accurate editorial incorporation of the previously approved change.
    [Show full text]
  • 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.
    [Show full text]
  • Safety Issues at the DOE Test and Research Reactors. a Report to the U.S
    DOCUMENT RESUME ED 299 107 SE 049 603 TITLE Safety Issues at the DOE Test and Research Reactors. A Report to the U.S. Department of Energy. INSTITUTION National Academy of Sciences - National Research Council, Washington, DC. Commission on Physical Sciences, Mathematics, and Resources. SPONS AGENCY Department of Energy, Washington, D.C. PUB DATE 88 CONTRACT DE-FG01-86ER35012 NOTE 151p.; Contains drawings and colored photographs which may not reproduce well. AVAILABLE FROMNational Research Council, Commission on Physical Sciences, Mathematics, and Resources, 2101 Constitution Avenue, NW, Washington, DC 20418 (free while supply lasts). PUB TYPE Reports - Evaluative/Feasibility (142) EDRS PRICE MF01/PC07 Plus Postage. DESCRIPTORS Accident Prevention; Engineering; Higher Education; *Mechanics (Process); Nuclear Energy; *Nuclear Physics; Nuclear Power Plants; *Nuclear Power Plant Technicians; *Nuclear Technology; Radiation Effects; Safety; Science Education; *Scientific Research IDENTIFIERS Department of Energy; National Academy of Sciences; *Nuclear Engineering; Nuclear Reactors; Nuclear Wastes ABSTRACT This report provides an assessment of safety issues at the Department if Energy (DOE) test and research reactors. Part A identifies six safety issues of the reactors. These issues include the safety design philosophy, the conduct of safety reviews, the performance of probabilistic risk assessments, the reliance on reactor operators, the fragmented character of the DOE management structure, and the safety implications of the current budgetary climate. Part B provides an assessment of technical issues to each of five reactors, such as (1) Advanced Test Reactor (ATR); (2) Experimental Breeder Reactor II (EBRII); (3) Fast Flux Test Facility (FFTF); (4) High Flux Beam Reactor (HFBR); and (5) High Flux Isotope Reactor (HFIR).
    [Show full text]
  • 18 IGORR Conference IAEA Workshop on Safety Reassessment
    18th IGORR Conference and IAEA Workshop 18th IGORR Conference and IAEA Workshop on Safety Reassessment of Research Reactors in Light of the Lessons Learned from the Fukushima Daiichi Accident, J7-TR-54790 International Conference Centre Sydney Darling Harbour, Sydney, Australia Sunday 3 – Thursday 7 December 2017 Sunday 3 December 17:00 Registration Reception Drinks and canapés Register for the Conference 18th IGORR Conference and IAEA Workshop Monday 4 December 08:20 Opening Session (Room C4.1) Chair: ANSTO Welcome to Country Welcome from ANSTO, IGORR & IAEA 09:00 General Session (Room C4.1) Chairs: David Vittorio & Gilles Bignan Andrea Borio di Tigliole: IAEA activities to support sustainable operation of and access to research reactors Gilles Bignan: The CEA scientific and technical offer as a designated ICERR by the IAEA: First feedback with the prime Affiliates Alexander Tuzov: RIAR as IAEA ICERR: Pilot technical cooperation projects and future prospects Sean O’Kelly: The first 50 years of operation of the ATR at the Idaho National Laboratory Khalid Almarri: A qualitative study for establishing the conditions for the successful implementation of public private partnerships in research reactor project in newcomer contries 10:40 Morning Tea Break (Room C4.4) 11:00 IAEA Workshop (Room C4.1) Chair: David Sears David Sears: IAEA Activities on the safety of Research Reactors Alexander Sapozhnikov: New safety requirements addressing feedback from the Fukushima Daiichi accident Mark Summerfield: Some thoughts on operator intervention arising
    [Show full text]
  • Winter 2013 Secret Weapons of the Secret City
    Vol. 19, No. 1 Newsletter of the China Lake Museum Foundation Winter 2013 Secret Weapons of the Secret City Fat Man and Little Boy. Of all the ―weapons that win wars,‖ the ones that can best lay claim to the title are the first atomic bombs, Fat Man and Little Boy, which helped to end World War II. China Lake was a major contributor to the success of those weapons. The U.S. initiated a program in 1942, under the Army Corps of Engineers, to build a weapon that would allow the U.S. to end the war without having to invade Japan. Several large engineering and production centers were set up at remote sites including sites in Tennessee, Washington (state), New Mexico, and California. In 1945, China Lake (then known as the Naval Ordnance Test Station or NOTS) carried out Project Camel, the code name for the station’s involvement in the Manhattan Project. China Lake’s Role: Non-Nuclear Components. An atomic bomb is essentially a conventional bomb with a nuclear core. The China Lake and the California Institute of Technology (Caltech) Team, experts at conventional explosives, was tasked to develop the non-nuclear explosive components of the atomic bomb; the conventional explosives were used to trigger the nuclear explosion. China Lake also performed detonator testing; mixed, melted, cast, and machined explosive shapes; air-dropped hundreds of bomb components and shapes from B-29 bombers; studied and solved flight problems; and conducted aero- ballistic tests to optimize aerodynamics and to test fuze functions. The team also checked out equipment procedures to be used in the tactical delivery of the atom bomb.
    [Show full text]