Analysis on the thermal-hydraulic characteristics for passive residual heat removal system of IPWRs

Due to compact configuration and the inherent safety functions,an integral pressurized water reactors(IPWRs) are suitable for the medium/small size nuclear power plants and marine nuclear power.Fundamental concept and general arrangement of the IPWRs in this paper is based on the same principle of the Inherent Safe UZrHx Power Reactor and the Russian ABV-6M IPWR.Overall design of the IPWR is as follows: the adoption of the arc plate fuels in core,casing once-through steam generator(OTSG),passive residual heat removal system(PRHRS) with three natural circulation loops and active shutdown cooling system(SCS).In the case of electricity shutdown accident,the reactor trips and PRHRS come into operation.By means of the RELAP5/MOD3.4 code,the thermal-hydraulic behaviors of the IPWR and its PRHRS safety characteristics are researched.The core decay heat may be safely removed.