2013 Annual Meeting
Session ID : M02
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Host: Atomic Energy Society of Japan
Water Flow Tests on Sloshing Behavior of Disrupted Core Pool in Fast Reactor:Validation of Thermal-hydraulic Analysis Code
*Tatsuhiro Abe, Shinya Nakayama, Tatsuya Matsumoto, Koji Morita, Isao Tatewaki, Tomoko Isizu, Hiroshi Endo
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