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Okubo, Tadatsune*; Tsukuda, Yoshiaki*; Kamimura, Katsuichiro*; Murai, Kenji*; Goto, Ken*; Doi, Soichi*; Senda, Yasuhide*; Kosaka, Yuji*; Kido, Toshiya*; Murata, Tamotsu*; et al.
Nihon Genshiryoku Gakkai-Shi, 43(9), p.906 - 915, 2001/09
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Hiyama, Toshiaki; Hiyama, Toshiaki; Takahashi, Toshio; Kamimura, Katsuichiro
Analytica Chimica Acta, 345(1), p.131 - 137, 1997/06
Times Cited Count：12 Percentile：44.06(Chemistry, Analytical)None
Kamimura, Katsuichiro; Yano, Soichiro; Kono, Shusaku; Kato, Masato; Morimoto, Kyoichi; Morihira, Masayuki; Kikuchi, Keiichi
PNC TN8410 97-067, 452 Pages, 1997/02
None
Kato, Masato; Sugata, Hiromasa*; Takahashi, Kuniaki; Kamimura, Katsuichiro
PNC TN8410 97-018, 38 Pages, 1997/01
None
Kato, Masato; ; Kamimura, Katsuichiro
Technical Commitee Meeting on Advances in Pellet Technology for Improved Performance and High Bumup, 0 Pages, 1996/00
None
Koyama, Kenji; ; Kamimura, Katsuichiro; Ikegami, Tetsuo; Noda, Kimio
PNC TN8440 96-001, 131 Pages, 1995/12
None
; ; ; Kamimura, Katsuichiro
Journal of Nuclear Materials, 218(1), p.1 - 7, 1995/07
Times Cited Count：2 Percentile：28.12(Materials Science, Multidisciplinary)None
Kato, Masato; Yano, Soichiro; ; Kamimura, Katsuichiro;
Donen Giho, (94), p.53 - 62, 1995/06
None
Kamimura, Katsuichiro; Iijima, Takashi*; Yano, Soichiro
PNC TN8410 95-296, 186 Pages, 1995/05
None
Kamimura, Katsuichiro; Kageyama, Tomio; Hiyama, Toshiaki; Yamamoto, Junta
PNC TN8430 95-005, 29 Pages, 1995/04
None
Nishiyama, Motokuni; Kamimura, Katsuichiro; Seki, Masayuki; Tsukada, Tatsuya*; Ishibashi, Fujio; Isaka, Kazuhiko*
PNC TN8410 95-046, 81 Pages, 1995/01
None
; Kamimura, Katsuichiro
Proceedings of International Topical Meeting on Light Water Reactor Fuel Performance, 0 Pages, 1994/07
Two rigs of plutonium-uranium mixed oxide(MOX) fuel rods have been irradiated in halden boiling water reactor (HBWR) to investigate mox fuel behavior for thermal reactor. objective of irradiation tests is to investigate fuel behavior as influenced by pellet shape, pellet surface treatment, pellet-cladding gap size and MOX fuel powder preparation process. The two rigs have instrumentations for in-pile measurements of the fuel center-line temperature, plenum pressure, cladding elongation and fuel stack length change. The data taken through in-operation instrumentations have been analyzed and compared with those from post-irradiation examination. The following observations are made. (1) PNC MOX fuels have achiived high burn-up as 57Gwd/t MOX (65Gwd/tm) at pellet peak without failure. (2) there
; ; Kamimura, Katsuichiro
Int. Topical Meeting on LWR Fuel Performance, 0 Pages, 1994/04
Two rigs of plutonium-uranium mixed oxide (MOX) fuel rods have been irradiated in halden boiling water reactor (HBWR) to investigate MOX fuel behaviour for thermal reactor. objective of irradiation tests is to investigate fuel behaviour as influenced by pellet shape, pellet surface treatment, pellet-cladding gap size and mox fuel powder preparation process. The two rigs have instrumentations for in-pile measurements of the fuel center-line temperature, plenum pressure, cladding elongation and fuel stack length change. The data taken through in-operation instrumentations have been analyzed and compared with those from post-irradiationexamination. The following observations are made. (1) pnc mox fuels have achived high burn-up as 59Gwd/t MOX (67Gwd/t m) at pellet peak without failure. (2) th
Kamimura, Katsuichiro; Sugaya, Shinichi; Fujita, Shinichi*; Hiyama, Toshiaki; Yamamoto, Junta
PNC TN8410 93-211, 47 Pages, 1993/09
None
*; Kamimura, Katsuichiro; Kodato, Kazuo; Yamaguchi, Toshihiro; *
PNC TN841 84-23, 190 Pages, 1984/05
no abstracts in English
