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Minato, Kazuo
Seramikkusu, 39(10), p.830 - 833, 2004/10
no abstracts in English
Iwase, Akihiro; Ishikawa, Norito; Iwata, Tadao*; Chimi, Yasuhiro; Nihira, Takeshi*
Physical Review B, 60(15), p.10811 - 10819, 1999/00
Times Cited Count：4 Percentile：28.67(Materials Science, Multidisciplinary)no abstracts in English
Minato, Kazuo; Fukuda, Kosaku; Sekino, Hajime; Ishikawa, Akiyoshi;
Journal of Nuclear Materials, 252, p.13 - 21, 1998/00
no abstracts in English
Minato, Kazuo; ; Sawa, Kazuhiro; Tobita, Tsutomu; Fukuda, Kosaku
JAERI-Tech 95-056, 45 Pages, 1996/01
no abstracts in English
Minato, Kazuo; ; Fukuda, Kosaku; *; *; *; *
Nuclear Technology, 111, p.260 - 269, 1995/08
Times Cited Count：4 Percentile：43.23(Nuclear Science & Technology)no abstracts in English
Ogawa, Toru; Fukuda, Kosaku; Kashimura, Satoru; Tobita, Tsutomu; Kobayashi, Fumiaki; ; ; ; Kikuchi, Teruo
Journal of the American Ceramic Society, 75(11), p.2985 - 2990, 1992/11
Times Cited Count：40 Percentile：84.42(Materials Science, Ceramics)no abstracts in English
Minato, Kazuo; Ogawa, Toru; Kashimura, Satoru; Fukuda, Kosaku; ; ;
J. Mater. Sci., 26, p.2379 - 2388, 1991/00
Times Cited Count：15 Percentile：61.58(Materials Science, Multidisciplinary)no abstracts in English
Hayashi, Kimio; Fukuda, Kosaku
Journal of Nuclear Science and Technology, 27(4), p.320 - 332, 1990/04
no abstracts in English
Ogawa, Toru; Fukuda, Kosaku
Surface Modification Technologies,III, p.309 - 320, 1990/00
no abstracts in English
Minato, Kazuo; ;
JAERI-M 87-024, 18 Pages, 1987/02
no abstracts in English
Minato, Kazuo; ; ;
JAERI-M 86-083, 27 Pages, 1986/06
no abstracts in English
Saeki, Masakatsu
Journal of Nuclear Materials, 131, p.32 - 36, 1985/00
Times Cited Count：43 Percentile：96.29(Materials Science, Multidisciplinary)no abstracts in English
; Ikawa, Katsuichi
JAERI-M 9568, 34 Pages, 1981/07
no abstracts in English
; Ikawa, Katsuichi; Iwamoto, K.
Journal of Nuclear Materials, 80(1), p.184 - 186, 1979/00
Times Cited Count：1no abstracts in English
Sawa, Kazuhiro*; Haseda, Masaya*; Aihara, Jun
no journal, ,
In high temperature gas-cooled reactors (HTGRs), Tri-isotropic (TRISO)-coated fuel particles are employed as fuel. In the high burnup coated fuel particle, stress due to fission gas pressure and irradiation-induced pyrolytic carbon (PyC) shrinkage is introduced into the coating layers and consequently the stress could cause failure of coating layers under high burnup irradiation condition. A failure model has developed to predict failure fraction of TRISO-coated particle under high burnup irradiation. In the model, failure probability is strongly dependent on the irradiation characteristics of PyC. This paper describes the outline of the failure model and evaluation result of high burnup fuel irradiation experiment by the model.
