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Takase, Kazuyuki; Yoshida, Hiroyuki; Akimoto, Hajime; Ose, Yasuo*
Nihon Konsoryu Gakkai Nenkai Koenkai 2005 Koen Rombunshu, p.231 - 232, 2005/08
no abstracts in English
Akimoto, Hajime; Tamai, Hidesada; Onuki, Akira; Takase, Kazuyuki
Nihon Konsoryu Gakkai Nenkai Koenkai 2005 Koen Rombunshu, p.229 - 230, 2005/08
A thermal-hydraulic research program for Reduced-Moderation Water Reactor (RMWR) has been performed since 2002. The RMWR has a tight-lattice core to attain the breeding of nuclear fuel for the effective use of Plutonium in a light-water reactor system. In this R&D program, large-scale thermal-hydraulic tests, several model experiments and development of advanced numerical analysis codes are being carried out to confirm the cooling performance in tight-lattice fuel assembly of the RMWR. In this paper, outline of the research program is described as well as the latest results of critical power measurement in the large-scale thermal-hydraulic tests and model experiments, which simulates the tight-lattice core of the RMWR.
Yoshikawa, Shinji
Nihon Konsoryu Gakkai Nenkai Koenkai 2005 Koen Rombunshu, p.311 - 312, 2005/08
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