Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 5; Validation of reactor analytical model for PLOHS events

Mori, Takero; Ohira, Hiroaki; Sotsu, Masutake; Fukano, Yoshitaka

no journal, , 

In order to evaluate the availability of the decay heat removal by natural circulation which is a measure for the Protected Loss of Heat Sink (PLOHS) in Fast Reactor, a whole core model which could simulate thermal hydraulics of each subassembly in a reactor was applied to Monju core. The Monju core model was validated by a test result of actual plant, MONJU. In addition, an analysis was conducted for PLOHS to investigate the applicability of this model.