Development of numerical simulation method for relocation behavior of molten materials in nuclear reactors, 4; Evaluation for the relocation behavior of molten materials on the corium spreading analysis

Yamashita, Susumu   ; Yoshida, Hiroyuki  ; Takase, Kazuyuki

In the Fukushima accidents, fuel assemblies which were installed in the reactors were reached a high temperature by stop of the core cooling system with a power station black-out. As a result, it is considered that the core degradation has been introduced because the melting of the fuel rods occurred and the melting behavior was expanded. In order to elucidate a progress of the melting phenomena in the reactor core, a numerical simulation code which can be precisely evaluated the melting phenomena is required. Therefore, we have been developing the numerical code named JUPITER to elucidate such phenomena. In the last report, we implemented multicomponent analysis function to the JUPITER and confirmed that it works well for the function in molten material relocation analysis including a heating and non heating material. In this study, we will present the result of comparison between the corium spreading experiment and its numerical result.