Small-Break Loss of Coolant Accident Analysis of the Integrated Pressurized Water Reactor

The pressurizer vapour space small-break loss of coolant accident is analyzed based on the nuclear thermal hydraulic transient analysis software RELAP5/SCDAP/MOD3.4 code. Transient characteristics of the Integrated Pressurized Water Reactor (IPWR) system pressure, core temperature, mass flow rate, reactor vessel water level are achieved. The influences of three different break areas are also studied and the conclusion is consistent with local experiment conclusion. The results show that the safety system of the IPWR can make sure the reactor core is under the water after the accident happens and the passive residual heat removal system can remove the core heat.