Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan
2007 Annual Meeting
Session ID : D14
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Analysis on reactor performance and safety characteristics of HTGR
(4) Development and validation of analytical methodology for coolant flow reduction test
*Shigeaki Nakagawa, Kuniyoshi Takamatsu, Tetsuaki Takeda, Minoru Goto, Hiroyuki Saito
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Keywords: HTGR, Numerical analysis, Safety characteristics, Reactor dynamics, HTTR
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[in Japanese]
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© 2007 Atomic Energy Society of Japan
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