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Kamiyama, Kenji; Matsuba, Kenichi; Isozaki, Mikio; Imaizumi, Yuya; Suzuki, Toru; Emura, Yuki
no journal, ,
no abstracts in English
Emura, Yuki; Matsuba, Kenichi; Isozaki, Mikio; Imaizumi, Yuya; Kamiyama, Kenji
no journal, ,
A series of simulation tests discharging a molten alloy with low-melting point into a shallow water pool is being conducted in order to investigate fuel-coolant interaction and sedimentation behavior of molten core materials on the structure of core inlet coolant plenum in the core disruptive accident of sodium-cooled fast reactors. The present study shows effects of the initial temperature of the molten alloy, the confined coolant volume, etc. on the test results.
Emura, Yuki; Isozaki, Mikio; Matsuba, Kenichi; Kamiyama, Kenji
no journal, ,
In core-disruptive accidents of sodium-cooled fast reactors, molten-core materials are discharged into a lower part of reactor vessel and are mixed with sodium there. In this study, molten stainless steel was poured into sodium and its behavior in the sodium was observed by a visualization system using X-ray.
Igarashi, Kai*; Sakai, Takaaki*; Kato, Shinya; Matsuba, Kenichi; Kamiyama, Kenji
no journal, ,
In order to clarify the accumulation behavior on the core disruptive accident in sodium cooled fast reactors, an analysis for the experiment in which the low-melting point alloy drop into a shallow water pool was conducted by using SIMMER code. In this presentation, the validation result for the analysis geometry model conducted by the comparison of the calculation result and experimental value is presented.
Matsushita, Hatsuki*; Kobayashi, Ren*; Sakai, Takaaki*; Kato, Shinya; Matsuba, Kenichi; Kamiyama, Kenji
no journal, ,
no abstracts in English