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First application of SIMMER-III to local fuel-coolant interactions in a simulated molten fuel pool

模擬溶融燃料プール中における局所的な溶融燃料-冷却材相互作用に対するSIMMER-IIIコードの予備的適用

Cheng, S.; 松場 賢一; 磯崎 三喜男; 神山 健司; 鈴木 徹; 飛田 吉春

Cheng, S.; Matsuba, Kenichi; Isozaki, Mikio; Kamiyama, Kenji; Suzuki, Toru; Tobita, Yoshiharu

Analyses of severe accidents for sodium-cooled fast reactors have shown that by assuming pessimistic conditions the accident might proceed into a transition phase where a whole-core-scale pool containing sufficient fuel to exceed prompt criticality by fuel compaction might be formed. Local fuel-coolant interaction in the pool is regarded as one of the probable initiators that could lead to such compactive fluid motions. From previous preliminary experimental analyses, it was recognized that for a given melt and water temperature within the non-film boiling range, with the increasing of water volume, a limited pressure buildup can be observed. In this study, to further understand this interaction, SIMMER-III, an advanced fast reactor safety analysis code, is utilized for analyses. It is found that the SIMMER-III code can reasonably simulate the transient pressure and temperature tendencies during local FCIs as understood from experiments. In addition, from the comparative analyses between different cases, the observed limited pressurization characteristics from experiments can be confirmed as well. To achieve a deeper and more systematic understanding on local FCIs, with the ongoing of experimental analyses, more numerical analyses over various situations, such as much difference in water subcooling, melt temperature as well as the water release site, have been also planned.

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