Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Kitamura, Akihiro; Okada, Takashi; Asazuma, Shinichiro; Uematsu, Shinichi; Ishibashi, Takashi
Proceedings of 12th International Conference on Nuclear Engineering (ICONE-12) (CD-ROM), 6 Pages, 2004/00
The gloveboxes and process equipment used at plutonium fuel handling facilities had to bereplaced due to deterioration or change of object.
Okada, Takashi; Uematsu, Shinichi; Tobita, Noriyuki; Kato, Junya
9th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM '03), 0 Pages, 2003/00
None
Uematsu, Shinichi; Tobita, Noriyuki; Kashiro, Kashio
WM'02, 0 Pages, 2002/00
None
Uematsu, Shinichi; Tobita, Noriyuki; Koakutsu, Toru
Proceedings of 8th International Conference on Radioactive Waste Management and Environmental Remediation (ICEM '01) (CD-ROM), 0 Pages, 2001/00
None
Uematsu, Shinichi; Mitsugi, Takeshi; ; Kobayashi, Tetsuro*; Yokoya, Jun*
Nihon Genshiryoku Gakkai-Shi, 39(10), p.870 - 880, 1997/10
Times Cited Count:1 Percentile:14.10(Nuclear Science & Technology)None
Onuki, Norihiko; ; Shuji, Yoshiyuki; Uematsu, Shinichi; ; ;
PNC TN8410 97-272, 143 Pages, 1997/08
None
Uematsu, Shinichi; ; Onuki, Norihiko; ;
ANS Topical Meeting on LWR Fuel Perfomance, 0 Pages, 1997/00
None
Yamaguchi, Takashi; Shuji, Yoshiyuki; Uematsu, Shinichi
Proceedings of ANS Topical Meeting on Advances in Nuclear Fuel Management II, 0 Pages, 1997/00
None
Uematsu, Shinichi; Yamaguchi, Takashi; ; Matsumoto, Mitsuo
Proceedings of International Conference on Future Nuclear Systems (GLOBAL'97), 0 Pages, 1997/00
None
; Uematsu, Shinichi
Specialists 'Meeting on Nuclear Fuel and Control Rods, 0 Pages, 1996/10
The Power Reactor and Nuclear Fuel Development Corporation(PNC)hasdeveloped the advanced thermal reactor(ATR). PNC is demonstrating MOX fuel utilization in a prototype of ATR, Fugen(165MWe), in which 638 MOX fuel assemblies have been loaded without a failure since 1979. PNC is developing the high burn-up MOX fuel for the ATR to contribute to MOX fuels for thermal reactors. The statistical design evalu
Uematsu, Shinichi; Kikuchi, Keiichi
Proceedings of 1994 International Topical Meeting on Light Water Reactor Fuel Performance, 0 Pages, 1994/00
None
Uematsu, Shinichi; ; Mitsugi, Takeshi
Proceedings of ANS International Topical Meeting on Light Water Reactor Fuel Performance, 0 Pages, 1994/00
None
Uematsu, Shinichi; ; ; Abe, Tomiyuki; Matsumoto, Mitsuo
Donen Giho, (87), p.53 - 61, 1993/09
None
Uematsu, Shinichi; ; ; Matsumoto, Mitsuo
ANP 92 INTERNATIONAL CONFTY OF ADVANCED NUCLEAR P, 2, 19-1 Pages, 1992/00
None