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Calabrese, R.*; Hirooka, Shun
Progress in Nuclear Energy, 178, p.105516_1 - 105516_11, 2025/01
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)Thermal creep is one of the key properties of mixed oxide (MOX) fuel for innovative fast reactors. Thermal creep of fuel affects markedly the interaction between the fuel and the cladding. A review of correlations available in the literature is presented. The effect of porosity, plutonium concentration, and stoichiometry are discussed also in the light of recent numerical results. Our analysis pointed out some inconsistencies concerning the modelling of the effect of porosity on diffusional creep and a re-evaluation of the effect of plutonium concentration. The discussion suggested that Evans's findings on the effect of stoichiometry should be better assessed as well as the level of increase in creep moving towards stoichiometry. Typical operating conditions of fast breeder reactors confirmed the need for an extension of porosity and temperature correlations' domains. Besides this, a new correlation based on a separate-effect approach has been proposed for fuel performance codes.
Takamatsu, Kuniyoshi; Nakagawa, Shigeaki
JAERI-Data/Code 2005-003, 31 Pages, 2005/06
JAERI-Data-Code-2005-003.pdf:4.83MB
Safety demonstration tests using the High Temperature engineering Test Reactor (HTTR) are in progress to verify the inherent safety features for High Temperature Gas-cooled Reactors (HTGRs). The coolant flow reduction test by tripping gas circulators is one of the safety demonstration tests. The reactor power safely brings to a stable level without a reactor scram and the temperature transient of the reactor-core is very slow. The TAC/BLOOST code was developed to analyze reactor and temperature transient during the coolant flow reduction test taking account of reactor dynamics. This paper describes the validation result of the TAC/BLOOST code with the measured values of gas circulators tripping tests at 30 % (9 MW). It was confirmed that the TAC/BLOOST code was able to analyze the reactor transient during the test.
Nakata, Tetsuo*; Katanishi, Shoji; Takada, Shoji; Yan, X.; Kunitomi, Kazuhiko
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.478 - 489, 2003/12
no abstracts in English
Nakano, Yoshihiro; Ichikawa, Hiroki; Nakajima, Teruo
Proc. of the 16th Int. Meeting on Reduced Enrichment for Research and Test Reactors, 0, p.313 - 320, 1994/03
no abstracts in English
Kunugi, Tomoaki; ;
Therm. Sci. Eng., 2(3), p.9 - 17, 1994/00
no abstracts in English
Ioka, Ikuo; Suzuki, Kunihiro; Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; ; Shimomura, Hiroaki
Nihon Genshiryoku Gakkai-Shi, 32(12), p.1221 - 1223, 1990/12
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)no abstracts in English
; Suzuki, Kunihiro; Hino, Ryutaro; Takase, Kazuyuki; Inagaki, Yoshiyuki; Ioka, Ikuo
Nucl. Eng. Des., 120, p.435 - 445, 1990/00
Times Cited Count：3 Percentile：39.96(Nuclear Science & Technology)no abstracts in English
; ; ; ; ; ; ;
JAERI-M 85-182, 304 Pages, 1985/11
no abstracts in English
; ; ; Sanokawa, Konomo
Nucl.Eng.Des., 83, p.91 - 103, 1984/00
Times Cited Count：4 Percentile：45.07(Nuclear Science & Technology)no abstracts in English
; ; ; ; ; ; ; ; ; ; et al.
JAERI-M 6895, 170 Pages, 1976/12
no abstracts in English
