Design and simulation of pressurizer safety valve test facility

Korean Hydro and Nuclear Power Company plans to build Pressurizer Safety Valve(PSV) test facility to provide a basis for safety analysis, such as loop seal purge and valve dynamics. This facility consists of the accumulator, test vessel, pressure relief tank, loop seal, heater, safety valves, pump, pipes, and auxiliaries. The facility's design pressure and temperature are 220 kg/cm2 and 380 .deg. C, respectively. The accumulator provides and heat source to the test vessel. The pressure of test vessel is controlled by the control valves installed between the accumulator and the test vessel. The PSV test facility design is verified by using the thermal-hydraulic analysis code GOTHIC-7.2a. The sizing of control valve to provide the required pressurization rate of the test vessel is determined by this test simulation. And it is found that the pressure vessel design is adequate and the reseating time of PSV is sufficient to model the overall overpressure transient of the nuclear power plants