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Titolo:
Evaluation procedures for irradiation effects and sodium environmental effects for the structural design of Japanese fast breeder reactors
Autore:
Asayama, T; Abe, Y; Miyaji, N; Koi, M; Furukawa, T; Yoshida, E;
Indirizzi:
Japan Nucl Cycle Dev Inst, Oarai Engn Ctr, Ibaraki, Osaka, Japan Japan Nucl Cycle Dev Inst Ibaraki Osaka Japan Ctr, Ibaraki, Osaka, Japan
Titolo Testata:
JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME
fascicolo: 1, volume: 123, anno: 2001,
pagine: 49 - 57
SICI:
0094-9930(200102)123:1<49:EPFIEA>2.0.ZU;2-3
Fonte:
ISI
Lingua:
ENG
Tipo documento:
Article
Natura:
Periodico
Settore Disciplinare:
Engineering, Computing & Technology
Citazioni:
33
Recensione:
Indirizzi per estratti:
Indirizzo: Asayama, T Japan Nucl Cycle Dev Inst, Oarai Engn Ctr, Ibaraki, Osaka, Japan Japan Nucl Cycle Dev Inst Ibaraki Osaka Japan i, Osaka, Japan
Citazione:
T. Asayama et al., "Evaluation procedures for irradiation effects and sodium environmental effects for the structural design of Japanese fast breeder reactors", J PRES VESS, 123(1), 2001, pp. 49-57

Abstract

In the structural design of fast breeder reactors, irradiation effects andsodium environmental effects on structural materials have to be taken intoaccount. In this paper, firstly, an evaluation procedure for irradiation effects on the mechanical properties of 316FR (FBR Grade 316 stainless steel) which is a newly developed stainless steel for the Japanese demonstrationfast breeder reactor is proposed. The procedure gives a limit of accumulated fast neutron fluence (E > 0.1 MeV) as afilnction of temperature, so thatthe minimum tensile fracture elongation of 10 percent, which is the threshold for material to stay ductile, is maintained. Furthermore, the proceduredetermined a creep life reduction factor and a creep rate increase factor as a function of accumulated thermal neutron fluence (E < 0.4 eV), within the limitation of the accumulated fast neutron fluence, to account for the creep life reduction and the increase of creep rate due to irradiation. Secondly, an evaluation procedure for sodium environmental effects on the integrity of 316FR and modified 9Cr-1Mo steel was proposed. It gave a corrosion allowance as a function of temperature, oxygen content, and service time, based on corrosion tests. It determined that no correction factors that correspond to sodium environment on design allowable stresses, etc., are needed, because no adverse effects of sodium on the mechanical properties of 316FR and modified 9Cr-1Mo steel were to be expected in the service conditions of FBRs. Both the procedures have been incorporated into the Japanese Elevated Temperature Structural Design Guide for Demonstration Fast Breeder Reactor.

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Documento generato il 04/04/20 alle ore 11:59:25