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Neuhold, R.J.; Marchaterre, J.F.; Waltar, A.E.
Westinghouse Hanford Co., Richland, WA (USA)1987
Westinghouse Hanford Co., Richland, WA (USA)1987
AbstractAbstract
[en] A new approach to achieving fast reactor safety goals is becoming really apparent in the US Fast Reactor Program. Whereas the ''defense is best'' philosophy still prevails, there has been a tangible shift toward emphasizing passive mechanisms to protect the reactor and provide public safety---rather than relying on add-on active, engineered safety systems. This paper reviews the technical basis for this new safety approach and provides discussion on its implementation in current US liquid metal-cooled reactor designs. 4 refs., 4 figs
Primary Subject
Source
1987; 12 p; ANS/ENS international conference on fast breeder reactor systems: experience gained and path to economical power generation; Richland, WA (USA); 13-17 Sep 1987; CONF-870917--9; Available from NTIS, PC A03/MF A01; 1 as DE89001118; Portions of this document are illegible in microfiche products.
Record Type
Report
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Conference
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BREEDER REACTORS, COMPUTER CODES, DEVELOPED COUNTRIES, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, LIQUID METAL COOLED REACTORS, NORTH AMERICA, PLUTONIUM REACTORS, POWER REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SAFETY, SODIUM COOLED REACTORS, TEST FACILITIES, TEST REACTORS
Reference NumberReference Number
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Neuhold, R.J.; Leggett, R.D.; Walters, L.C.; Matthews, R.B.
Hanford Engineering Development Lab., Richland, WA (USA); USDOE, Washington, DC; Argonne National Lab., Idaho Falls, ID (USA); Los Alamos National Lab., NM (USA)1986
Hanford Engineering Development Lab., Richland, WA (USA); USDOE, Washington, DC; Argonne National Lab., Idaho Falls, ID (USA); Los Alamos National Lab., NM (USA)1986
AbstractAbstract
[en] The fuels development program of the United States is described for liquid metal reactors (LMR's). The experience base, status and future potential are discussed for the three systems - oxide, metal and carbide - that have proved to have high reliability. Information is presented showing burnup capability of the oxide fuel system in a large core, e.g., FFTF, to be 150 MWd/kgM with today's technology with the potential for a capability as high as 300 MWd/kgM. Data provided for the metal fuel system show 8 at. % being routinely achieved as the EBR-II driver fuel with good potential for extending this to 15 at. % since special test pins have already exceeded this burnup level. The data included for the carbide fuel system are from pin and assembly irradiations in EBR-II and FFTF, respectively. Burnup to 12 at. % appears readily achievable with burnups to 20 at. % being demonstrated in a few pins. Efforts continue on all three systems with the bulk of the activity on metal and oxide
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Secondary Subject
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May 1986; 15 p; International conference on reliable fuels for liquid metal reactors; Tucson, AZ (USA); 7-11 Sep 1986; CONF-860931--18; Available from NTIS, PC A02/MF A01; 1 as DE87007702; Portions of this document are illegible in microfiche products.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
AIR COOLED REACTORS, BREEDER REACTORS, DEFORMATION, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUELS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HOMOGENEOUS REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MATERIALS, NUCLEAR FUELS, POWER REACTORS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SODIUM COOLED REACTORS, SOLID FUELS, SOLID HOMOGENEOUS REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS
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AbstractAbstract
No abstract available
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Journal Article
Literature Type
Progress Report
Journal
Nuclear Science and Engineering; v. 43 p. 74-86
Country of publication
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AbstractAbstract
No abstract available
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Journal Article
Journal
Nuclear Science and Engineering; v. 39 p. 14-24
Country of publication
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AbstractAbstract
[en] Studies were recently performed for the U.S. DOE by reactor design organizations to determine the capability of new evolutionary and existing light water reactors to burn excess weapons grade plutonium in the form of mixed oxide fuels (MOX). A subsequent evaluation by DOE has been completed. This paper presents information from these reports
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Source
Annual meeting of the American Nuclear Society (ANS); Philadelphia, PA (United States); 25-29 Jun 1995; CONF-950601--
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Journal Article
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Conference
Journal
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Neuhold, R.J.; Lewellen, J.W.
Proceedings of the conference on computational methods in nuclear engineering. Vol. II1975
Proceedings of the conference on computational methods in nuclear engineering. Vol. II1975
AbstractAbstract
[en] Past and current coordinating procedures related to computer coding are reviewed and assessed with respect to their general applicability in the Civilian Reactor Program. Elements of closely coordinated activities specialized to a single discipline such as reactor physics which could have general utility are identified. 11 references. (U.S.)
Primary Subject
Source
Du Pont de Nemours (E.I.) and Co., Aiken, S.C. (USA). Savannah River Lab.; Energy Research and Development Administration, Aiken, S.C. (USA). Savannah River Operations Office; p. VI.1-VI.8; 1975; ANS computational methods in nuclear energy; Charleston, South Carolina, USA; 15 Apr 1975
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Report
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Conference
Report Number
Country of publication
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AbstractAbstract
[en] A nationally coordinated materials development program for fast breeder reactors is being conducted to improve the economy and reliability of replaceable core components. The program is comprised of three parallel paths, including reference alloys for present applications, second-generation alloys for near-term applications, and third-generation alloys for longer term applications. Reference alloy work is complete, with the major program emphasis being placed on qualification of titanium-modified Type 316 stainless steel (D9) for core applications. Ferritic alloy, HT-9, has been identified as an excellent duct material, and qualification of this alloy is being phased in as D9 work is completed. Another four alloys have been identified as potential cladding materials and are scheduled for completed development and application by 1988
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Secondary Subject
Record Type
Journal Article
Journal
Nuclear Technology; ISSN 0029-5450; ; v. 57(3); p. 426-435
Country of publication
AUSTENITIC STEELS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, ELEMENTS, EPITHERMAL REACTORS, FAST REACTORS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MARTENSITIC STEELS, MATERIALS, METALS, MOLYBDENUM ADDITIONS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, REACTOR COMPONENTS, REACTORS, STAINLESS STEELS, STEELS, TRANSITION ELEMENTS, VANADIUM ADDITIONS
Reference NumberReference Number
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AbstractAbstract
[en] The liquid metal reactor (LMR) safety R and D program in the U.S. is presently focused on support of two modular innovative reactor concepts: PRISM - the General Electric Power Reactor Inherently Safe Module and SAFR - the Rockwell International Sodium Advanced Fast Reactor. These reactor plant concepts accommodate the use of either oxide fuel or the metal fuel which is under development in the Argonne National Laboratory (ANL) Integral Fast Reactor (IFR) program. Both concepts emphasize prevention of accidents through enhancement of inherent and passive safety characteristics. Enhancement of these characteristics is expected to be a major factor in establishing new and improved safety criteria and licensing arrangements with regulatory authorities for advanced reactors. Limited work is also continuing on the Large Scale Prototype Breeder (LSPB), a large pool plant design. Major elements of the current and restructured safety program are discussed. (author)
Primary Subject
Source
British Nuclear Energy Society, London; 535 p; ISBN 0 7277 0359 5 (2 VOL SET); ; 1986; p. 9-12; BNES; London (UK); International conference on science and technology of fast reactor safety; Guernsey (UK); 12-16 May 1986; price Pound 150
Record Type
Book
Literature Type
Conference
Country of publication
ACCIDENTS, AIR COOLED REACTORS, BREEDER REACTORS, DEVELOPED COUNTRIES, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FBR TYPE REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HOMOGENEOUS REACTORS, LMFBR TYPE REACTORS, NORTH AMERICA, POWER REACTORS, REACTORS, REGULATIONS, RESEARCH AND TEST REACTORS, SAFETY, SODIUM COOLED REACTORS, SOLID HOMOGENEOUS REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The authors discuss how anew approach to achieving fast reactor safety goals is becoming apparent in the U.S. Fast Reactor Program. Whereas the defense-in-depth philosophy still prevails, there has been a tangible shift toward emphasizing passive mechanisms to protect the reactor and provide public safety rather than relying on add-on active, engineered safety systems. Intrinsic reactivity feedback mechanisms, based on fundamental nuclear cross section and material motion changes with temperatures, combined with passive methods to assure removal of decay heat, are being quantified and included in analysis techniques to demonstrate the exceptional robustness of current advanced liquid-metal-cooled reactor designs in the United States
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Journal Article
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AbstractAbstract
[en] Current FBR fuel systems are limited in lifetime by distortions of the hexagonal ducts. Structural materials resistant to radiation induced creep and swelling have been developed. Alloys such as a martensitic alloy (HT-9) shows little distortion after 4 irradiation cycles (1.6 x 1023 n/cm at energies >0.1 MeV). Several fuel assemblies with D-9 austenitic/stainless steels are under irradiation in the FFTF, and HTO ducts have been manufactured for fuel assemblies under construction. The evolution of low swelling duct materials has required the use of low swelling cladding materials for high burnup (>100 MWd.kg) fuel assemblies to obtain a match in swelling of pin bundle and duct. (U.K.)
Original Title
LMFBRs
Primary Subject
Record Type
Journal Article
Journal
Nuclear Engineering International; ISSN 0029-5507; ; v. 26(320); p. 35-37
Country of publication
ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, CONVERSION RATIO, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SODIUM COOLED REACTORS, STEELS, TEST REACTORS, TRANSITION ELEMENT ALLOYS
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