JUPITERコードによる過酷時燃料要素内の温度分布と溶融移行挙動に関する数値的検討

Abstract

In order to precisely investigate molten core relocation behavior in the Fukushima Daiichi nuclear power station, we have developed the detailed and phenomenological numerical simulation code named JUPITER for predicting the molten core behavior including solidification and relocation based on the three-dimensional multiphase thermal-hydraulic simulation models. In order to evaluate the interface physics such as radiation model, oxidization model and eutectic reaction model, at first, we implemented the simple radiation model to the JUPITER. This paper reports the validity of the radiation model by the two dimensional simulation under the simple fuel element geometry.