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McDonald, J.S.; Campise, A.V.; Brunings, J.
Optimisation of sodium-cooled fast reactors. Proceedings of the international conference organized by the British Nuclear Energy Society in London, 28 November - 1 December 19771978
Optimisation of sodium-cooled fast reactors. Proceedings of the international conference organized by the British Nuclear Energy Society in London, 28 November - 1 December 19771978
AbstractAbstract
[en] The AI-PLBR breeder plant design prepared for ERDA and EPRI is of 1000 MWe size, utilizing a loop-type sodium system configuration and producing 2200 psig/8500F steam. A 'bullseye' core geometry type sodium system configuration and is employed with Pu02-UO2 fuel and UO2 fertile material. The reactor outlet coolant temperature is 9300F. A modified 'A'-frame refueling system is employed, which is capable of handling 1/3 of a core loading in 12 days. An inducer-type mechanical pump is used in the primary circuit because of its excellent NPSH characteristics. Hockey sticks steam generators are used to produce near-fossil steam conditions at the turbine throttle. The balance of plant (BOP) design was developed by the architectural-engineering firm of Burns and Roe. It includes Allis-Chalmers - KWU 1800-rpm tandem-compound turbine, selected with high-,intermediate-, and two double-flow low-pressure cylinders equipped with two moisture separator cyclones. A design feature to enhance the licensability of the reference design is the three-level Decay Heat Removal System (DHRS), which consists of normal, backup, and diverse decay heat removal paths. The Atomics International PLBR design illustrated the technical soundness of the LMFBR system for meeting the world's long-term electrical energy supply needs. The design includes design features to assure licensability and innovative engineering features to enhance reliability, constructability, economics, and U.S. utility grid compatibility. The design concept provides a sound basis for the future detailed design of a prototype plant and subsequent development of larger LMFBR plants. (author)
Primary Subject
Source
British Nuclear Energy Society, London; p. 239-246; ISBN 0 7277 0054 5;
; 1978; p. 239-246; Thomas Telford for the British Nuclear Energy Society; London; International conference on optimisation of sodium-cooled fast reactors; London, UK; 28 Nov - 1 Dec 1977

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AbstractAbstract
[en] The background and current developments relating to the PLBR reactor are reviewed
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39. annual meeting of the American Power Conference; Chicago, IL, USA; 18 - 20 Apr 1977; CONF-770403--
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Proceedings of the American Power Conference; v. 39 p. 152-155
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Anderson, C.A. Jr.
Optimisation of sodium-cooled fast reactors. Proceedings of the international conference organized by the British Nuclear Energy Society in London, 28 November - 1 December 19771978
Optimisation of sodium-cooled fast reactors. Proceedings of the international conference organized by the British Nuclear Energy Society in London, 28 November - 1 December 19771978
AbstractAbstract
[en] The optimization of the Westinghouse/Stone and Webster Prototype Large Breeder Reactor (PLBR) is described. This reactor plant, designed for ERDA and EPRI, resulted from optimization and tradeoffs on plant size, number of loops, steam cycles, system temperature, pump location, refueling concept, reactor shut-down system logic, control system logic, steam generating system, residual heat removal system, core arrangement and reactor vessel. The result is a three loop LMFBR rated at 1000 MWe gross with sodium entering the reactor vessel at 6500F (3450C) and leaving at 9500F) (5100C). The reactor vessel has a flat closure head on top, containing three rotating plugs on which are mounted the upper internals structure and the in-vessel transfer machine. The core has three radial layers of core material separating four radial blanket regions. An inclined refueling chute penetrates the reactor vessel. Plant efficiency of 37% is achieved with the use of once-through steam generators operating in the modified Sulzer mode, producing 2200 psi, 8500F (15.2 x 106 pa/4550C) steam. The residual heat removal system (RHRS) consists of three independent heat removal paths in which the intermediate sodium is cooled in air blast heat exchangers (author)
Primary Subject
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British Nuclear Energy Society, London; p. 247-259; ISBN 0 7277 0054 5;
; 1978; p. 247-259; Thomas Telford for the British Nuclear Energy Society; London; International conference on optimisation of sodium-cooled fast reactors; London, UK; 28 Nov - 1 Dec 1977

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Book
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Conference
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INIS VolumeINIS Volume
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Horst, K.M.; Gibson, A.S.; Davies, S.M.; Golan, S.
Optimisation of sodium-cooled fast reactors. Proceedings of the international conference organized by the British Nuclear Energy Society in London, 28 November - 1 December 19771978
Optimisation of sodium-cooled fast reactors. Proceedings of the international conference organized by the British Nuclear Energy Society in London, 28 November - 1 December 19771978
AbstractAbstract
[en] The General Electric/Bechtel PLBR is a conservatively designed 1000 MWe gross (914 MWe net) plant which gives confidence that a practical LMFBR can be built for U.S. application. A significant finding is that the LMFBR achieves lowest costs with a low reactor outlet temperature (4680C) and a low pressure (6.89 x 106 Pa) saturated steam cycle. Moreover, the risks of failing to meet performance or other goals are lower for these cycle conditions than for higher temperature superheat cycle conditions. (author)
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British Nuclear Energy Society, London; p. 223-237; ISBN 0 7277 0054 5;
; 1978; p. 223-237; Thomas Telford for the British Nuclear Energy Society; London; International conference on optimisation of sodium-cooled fast reactors; London, UK; 28 Nov - 1 Dec 1977

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Book
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Conference
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AbstractAbstract
No abstract available
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ANS winter meeting; San Francisco, CA, USA; 27 Nov 1977; See CONF-771109--. Published in summary form only.
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Journal Article
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Transactions of the American Nuclear Society; v. 27 p. 718-721
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AbstractAbstract
[en] The SNR-300 in Kalkar was considered to be an important project in European fast breeder development. The nuclear power plant was financed, developed and built in a joint German-Belgian-Netherlands collaborative effort, and was ready technically in June 1986 to accomodate the fuel assemblies and for the start of nuclear commissioning. Although the decision to not start up the SNR-300 de facto means opting out of a long term scheme of European collaboration in the development of breeder reactors, and the failure to abide by contractual agreements has financial consequences for Germany, the SNR-300 project was discontinued for political reasons in March 1991. (orig.)
[de]
In der europaeischen Schnellbrueterentwicklung galt der SNR-300 in Kalkar als ein wichtiges Projekt. Das Kernkraftwerk wurde in deutsch-belgisch-niederlaendischer Zusammenarbeit finanziert, entwickelt und errichtet und stand 1985/86 technisch zur Aufnahme der Brennelemente sowie fuer den Beginn der nuklearen Inbetriebnahme bereit. Obwohl der Verzicht auf die Inbetriebnahme des SNR-300 de facto einen Ausstieg aus einer langfristig angelegten europaeischen Zusammenarbeit in der Brutreaktorenentwicklung bedeutet und fuer Deutschland durch die Nichterfuellung vertraglicher Vereinbarungen finanzielle Konsequenzen entstehen, wurde das Projekt SNR-300 im Maerz 1991 aus politischen Gruenden beendet. (orig.)Original Title
Der Kalkar-Brueter steht jetzt in Japan
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AbstractAbstract
No abstract available
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ANS winter meeting; San Francisco, CA, USA; 27 Nov 1977; See CONF-771109--. Published in summary form only.
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Journal Article
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Conference
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Transactions of the American Nuclear Society; v. 27 p. 721-722
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Rasmuson, D.M.; Wilson, J.R.; Burdick, G.R.
Idaho National Engineering Lab., Idaho Falls (USA)1979
Idaho National Engineering Lab., Idaho Falls (USA)1979
AbstractAbstract
[en] The prototype large breeder reactor (PLBR) is a 1000 MWe sodium cooled fast breeder reactor designed to succeed the Clinch Breeder Reactor and verify scaling laws. Several conceptual PLBR designs have been presented for consideration. A procedure is needed for the conceptualization of, evaluation of, and selection between such designs. This paper presents a method that can be effectively used to: (1) allocate optimal component redundancy, (2) evaluate design trade-offs, and (3) help in design finalization. The procedure is applied to three diverse design options for a shutdown heat removal system (SHRS). The selected configuration is analyzed for potential common cause failures
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1979; 5 p; International meeting on fast reactor safety technology; Seattle, WA, USA; 19 - 23 Aug 1979; Available from NTIS., PC A02/MF A01
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Report
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Orechwa, Y.; Su, S.F.; Barthold, W.P.
Argonne National Lab., IL (USA)1978
Argonne National Lab., IL (USA)1978
AbstractAbstract
[en] A critical analysis of the core/blanket complex as defined in the Phase A LMFBR Pool Guidelines was performed with respect to consistency and feasibility of the nuclear, thermal and mechanical design assumptions. Recommendations were made for changes in fuel assembly and blanket assembly design, core configuration and orificing
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Oct 1978; 59 p; Available from NTIS., PC A04/MF A01
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[en] Commercial acceptance of the liquid metal reactor had its beginning with the Fermi reactor, over two decades ago. The pattern of industrialization since that time is discussed, contrasting domestic and foreign experience. The recent termination of the Clinch River reactor project marks a watershed in the U.S. approach towards commercialization. The increased emphasis on achieving cost competitive designs reflects an awareness that barriers to industrialization are institutional and financial, and not technological
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Intersociety energy conversion engineering conference; San Francisco, CA (USA); 19-24 Aug 1984; CONF-840804--
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Journal Article
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Proceedings, Intersociety Energy Conversion Engineering Conference; ISSN 0146-955X;
; v. 3 p. 1588-1591

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