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Fukaya, Yuji; Okita, Shoichiro; Sasaki, Koei; Ueta, Shohei; Goto, Minoru; Ohashi, Hirofumi; Yan, X.
Nuclear Engineering and Design, 399, p.112033_1 - 112033_9, 2022/12
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Kernel migration of TRi-structural ISOtropic (TRISO) fuel for High Temperature Gas-cooled Reactor (HTGR) has been analyzed to investigate the potential dominating effects. Kernel migration is a major fuel failure mode and dominant to determine the lifetime of the fuel for High Temperature engineering Test Reactor (HTTR). However, this study shows that the result and reliability depend on the evaluation method. The evaluation method used in this study takes into account of actual distribution of Coated Fuel Particles (CFPs) and the resulting heterogeneous fuel temperature calculation with such distribution. The result shows that the Kernel Migration Rate (KMR) is predicted to be about 10% less compared with the most conservative evaluation.
Hagiwara, Masaki
Genshiryoku Nenkan 2001/2002-Nen Ban, p.164 - 170, 2001/11
no abstracts in English
Fujikawa, Seigo
Genshiryoku Nenkan 2000/2001-Nen Ban, p.209 - 214, 2000/10
no abstracts in English
Ohshima, Hiroyuki; Sakai, Takaaki; ; Yamaguchi, Akira; Nishi, Yoshihisa*; Ueda, Nobuyuki*; *
JNC TN9400 2000-077, 223 Pages, 1999/05
JNC-TN9400-2000-077.pdf:6.24MB
The feasibility study (Phase l) is being carried out at JNC to build up new design concepts of practical fast reactors (FRs) from the viewpoint of economy, safety, effective use of resources, reduction of environmental burden and non-proliferation. This report describes the results of the investigation, related to decay heat removal, core/fuel-assembly thermal-hydraulics and thermal-hydraulic correlations, that was performed in fiscal l999 as a part of the feasibility study. ln the study of the decay heat removal, the effects of several design parameters on the performance of the reactor vessel auxiliary cooling system (RVACS) in a middle-scale sodium-cooled FR were clarified by using a plant dynamic analysis code. The upper limit of RVACS performance was preliminarily estimated at approximately 0.5
0.6 MWe. Numerical methods for the plant dynamic analysis of gas-and heavy-metal-cooled FRs were also developed. They were applied to the preliminary calculations of the transition from scram to natural circulation and the transient characteristics in tentative plant design concepts were clarified. ln addition, a dimensionless number indicating natural circulation performance was deduced for the comparison of several plant design concepts. With respect to the core/fuel-assembly thermal-hydraulics, numerical analysis methods were improved for the pin-type fuel assembly of gas-and heavy-metal-cooled FRs, the coated-particle- type fuel assembly of helium-gas-cooled FR, and the ductless core of sodium-and heavy-metal-cooled FRs. As preliminary evaluations, thermal-hydraulics in the heavy-metal-cooled FR fuel assembly was compared with sodium-cooled one and thermal-hydraulic analyses of carbon-dioxide- and helium-gas-cooled FR fuel assemblies were performed. The analysis for the fuel assembly with inside duct of sodium-cooled FR was also carried out. The correlations of pressure loss and heat transfer coefficient were investigated for the thermal-hydraulic ...
Fujikawa, Seigo; Hagiwara, Masaki
Genshiryoku Nenkan 1999/2000-Nen Ban, p.173 - 177, 1999/00
no abstracts in English
Hagiwara, Masaki; Shigemoto, Masamitsu; Fujikawa, Seigo
Genshiryoku Nenkan '98/'99-Nen Ban, p.166 - 170, 1998/00
no abstracts in English
Power Reactor and Nuclear Fuel Development Corporation
PNC TN9360 94-002, 100 Pages, 1994/02
no abstracts in English
Power Reactor and Nuclear Fuel Development Corporation
PNC TN9360 94-001, 95 Pages, 1994/02
no abstracts in English
Baba, Osamu
Nihon Kikai Gakkai Doryoku Enerugi Shisutemu Bumon Nyusu Reta, 0(7), p.4 - 5, 1993/11
no abstracts in English
Katagiri, Masaki; Kishimoto, Maki; Ito, Hirokuni; ; Fukushima, Masao; Okawa, Hiroshi;
Nuclear Instruments and Methods in Physics Research A, 327, p.463 - 468, 1993/00
Times Cited Count：3 Percentile：43.06(Instruments & Instrumentation)no abstracts in English
Katagiri, Masaki; Kishimoto, Maki; Ito, Hirokuni; Fukushima, Masao; Okawa, Hiroshi; ; ; Tobita, Tsutomu
Journal of Nuclear Science and Technology, 29(10), p.957 - 965, 1992/10
no abstracts in English
Enerugi Rebyu, 11(10), p.11 - 15, 1991/09
no abstracts in English
Katagiri, Masaki; Kishimoto, Maki; Terada, Hiromi; ; *; ; Ito, Hirokuni; ; Kobayashi, Fumiaki
IEEE Transactions on Nuclear Science, 37(3), p.1400 - 1404, 1990/06
Times Cited Count：3 Percentile：45.11(Engineering, Electrical & Electronic)no abstracts in English
Shigen Tekunoroji, (221), p.16 - 20, 1985/00
no abstracts in English
; Ikawa, Katsuichi; Iwamoto, K.
J.Mater.Sci., 14(1), p.125 - 132, 1979/00
Times Cited Count：21no abstracts in English
; ; ; ; ; *; *; *; *; *
Nihon Genshiryoku Gakkai-Shi, 21(3), p.245 - 267, 1979/00
Times Cited Count：3no abstracts in English
; ; *
JAERI-M 7415, 124 Pages, 1977/12
no abstracts in English
*; *; Iwamoto, K.
Nihon Genshiryoku Gakkai-Shi, 18(5), p.277 - 285, 1976/05
no abstracts in English
