Safety Analysis of JSCWR

Abstract

In order to assess viability of the Japanese Super-Critical Water-cooled Reactor (JSCWR) concept, which is a pressure-vessel type, thermal spectrum SCWR, a series of safety analyses have been conducted. The safety system of the JSCWR is designed with referring to that of BWRs. Ten abnormal transients and five design basis accidents, including LOCAs, are selected from those of current LWRs. Although the safety analyses here are not for licensing but for developing and understanding the JSCWR concept, the trend of the analysis results implies that there is no critical problem in the safety of the JSCWR concept from the viewpoint of its viability and it will encourage the next R&D step of the JSCWR.