田上 慎一 TANOUE Shinichi

ID:9000005884705

九州大 Kyushu University (2004年 CiNii収録論文より)

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  • Analysis for Large Bubble Transient Behavior by Reactor Safety Analysis Code  [in Japanese]

    MATSUMOTO Tatsuya , MORITA Koji , TANOUE Shinichi , FUKUDA Kenji , TOBITA Yoshiharu , YAMANO Hidemasa , SATO Ikken

    Transient behavior of the single and huge bubble discharged from the lower side into the water pool with about 0.3MPa was analyzed by using reactor safety analysis code (SIMMER-III). In this analysis, …

    The proceedings of the JSME annual meeting 2004.3(0), 225-226, 2004

    J-STAGE 

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