炉心安全解析コードを用いた巨大気泡の過渡挙動の解析(原子炉伝熱流動解析の革新(3),原子炉伝熱流動解析の革新)

概要

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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, it was verified that the condensation behavior of the bubble of nitrogen, steam and the mixture steam when there was non-condensable gas in the bubble enough and the bubble was grown up by the strong effect of condensation inhibition were reproduced comparatively well. Moreover, it was examined that the improvement of a physical model for the condensation behavior of the mixture steam was more necessary when the effect of the condensation inhibition of non-condensable gas was small and the gas phase was condensed rapidly.
2004-09-04