Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Nakamura, Hirofumi; Nagai, Toshihisa; Suto, Toshiyuki; Kosaka, Ichiro; Nakazaki, Katsutoshi; Suto, Shinya; Nakamura, Tomotaka; Nakabayashi, Hiroki; Hayashi, Naoto; Sumida, Daisaku
JAEA-Technology 2008-077, 276 Pages, 2008/12
JAEA-Technology-2008-077.pdf:25.66MB
Japan Atomic Energy Agency (JAEA) has been conducting "Fast Reactor Cycle Technology Development Project (FaCT Project)" for the purposes of researching and developing the technologies for the fast breeder reactor cycle commercialization since Japanese fiscal year (JFY) 2007. Based on the above R&D program for reprocessing system, the engineering-scale hot test would provide demonstration data on the specification, operation and maintenance of the adapted innovative technologies, system and plant. And more, these results would be fed to the design of the demonstration facility planning on the FaCT project road map. This report is the interim report of design studies about the engineering-scale hot test facility and includes not only design of the equipment and facility, but also consideration for design principle, requirements and facility basic planning.
Ojima, Hisao; Hayashi, Naoto; Nagai, Toshihisa; Fujita, Yuji; Kawata, Tomio
Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 5 Pages, 2005/10
This paper mentions a preliminary evaluation on the typical LWR-to-FBR transition scenarios. Deployment rate of FBRs is strongly connected with replacement rate of LWRs, however, the transition should be seen as a matter of the optimization of fuel cycle systems. Based on the Pu balance evaluation, it seems definitely necessary to save an adequate amount of LWR spent fuels before beginning the deployment of FBRs. The mission of the second LWR fuel reprocessing plant in Japan will most provably be to feed Pu needed for starting up new FBRs. Along with the Pu utilization, especially as LWR-MOX fuel, the accumulation of minor actinides(MAs) in the high-level radioactive waste will become dominant and finally result in larger number of vitrified HLW because of heat generation from MAs. MA recovery cycle combined with the FBR will gives successful solution on this matter. Requirements on the next generation reprocessing plant, which corresponds to the transition scenario, are studied and innovative concept named
Narita, Osamu; Ishida, Junichiro; Katagiri, Hiromi; Hayashi, Naomi; Miyagawa, Naoto; Watanabe, Hitoshi; Kobayashi, Mitsuru; Namiki, Atsushi; Sumiya, Shuichi; ; et al.
PNC TN8420 89-009, 238 Pages, 1989/08
None
Iwai, Hiroki; Hayashi, Hirokazu; Mori, Naoto; Sano, Kazuya; Morishita, Yoshitsugu; Shigeta, Tatsuo*
no journal, ,
no abstracts in English
Hayashi, Hirokazu; Mori, Naoto; Sano, Kazuya; Morishita, Yoshitsugu
no journal, ,
no abstracts in English
Hayashi, Hirokazu; Mori, Naoto; Kitamura, Koichi; Sano, Kazuya
no journal, ,
no abstracts in English
Mori, Naoto; Sano, Kazuya; Hayashi, Hirokazu; Iwai, Hiroki; Shigeta, Tatsuo*
no journal, ,
no abstracts in English
Matsuda, Yasuhiro*; Okuyama, Katsushi*; Komatsu, Hisanori*; Oki, Saiko*; Hashimoto, Naoki*; Sano, Hidehiko*; Yamamoto, Hiroko*; Iwami, Yukiteru*; Hayashi, Mikako*; Nomachi, Masaharu*; et al.
no journal, ,
no abstracts in English
Tsuchida, Daisuke; Hayashi, Hirokazu; Kitayama, Naoki; Mori, Naoto
no journal, ,
no abstracts in English
Hayashi, Naoto; Kamiya, Masayoshi; Takata, Takeshi; Takeuchi, Masayuki; Sato, Akira*; Nishimura, Masashi*
no journal, ,
no abstracts in English