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Journal Articles

The Analysis for Ex-Vessel debris coolability of BWR

Matsumoto, Toshinori; Iwasawa, Yuzuru; Ajima, Kohei*; Sugiyama, Tomoyuki

Proceedings of Asian Symposium on Risk Assessment and Management 2020 (ASRAM 2020) (Internet), 10 Pages, 2020/11

The probability of ex-vessel debris coolability under the wet cavity strategy is analyzed. The first step is the uncertainty analyses by severe accident analysis code MELCOR to obtain the melt condition. Five uncertain parameters which are relating with the core degradation and transfer process were chosen. Input parameter sets were generated by LHS. The analyses were conducted and the conditions of the melt were obtained. The second step is the analyses for the behavior of melt under the water by JASMINE code. The probabilistic distribution of parameters are determined from the results of MELCOR analyses. Fifty-nine parameter sets were generated by LHS. The depth of water pool is set to be 0.5, 1.0 and 2.0 m. Debris height were compared with the criterion to judge the debris coolability. As the result, the success probability of debris cooling was obtained through the sequence of calculations. The technical difficulties of this evaluation method are also discussed.

Oral presentation

Study on molten core coolability under precautionary water injection into containment vessel, 1; Development of breakup particle agglomeration model in JASMINE

Matsumoto, Toshinori; Kawabe, Ryuhei; Ajima, Kohei; Sugiyama, Tomoyuki; Maruyama, Yu

no journal, , 

no abstracts in English

Oral presentation

Study on molten core coolability under precautionary water injection into containment vessel, 2; Analysis by improved melt spreading model in JASMINE

Kawabe, Ryuhei; Matsumoto, Toshinori; Ajima, Kohei; Sugiyama, Tomoyuki; Maruyama, Yu

no journal, , 

no abstracts in English

Oral presentation

Evaluation of molten core coolability in containment vessel using JASMINE code

Iwasawa, Yuzuru; Matsumoto, Toshinori; Kawabe, Ryuhei; Ajima, Kohei; Sugiyama, Tomoyuki; Maruyama, Yu

no journal, , 

For assessment the molten core coolability during severe accident in LWRs, we improved the models in the JASMINE code regarding to agglomeration of melt particles and melt spreading in containment vessel based on the DEFOR-A and the PULiMS experiments conducted by KTH. The improved models generally show good agreement with these experimental results.

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