User-Defined Modeling of Pressurized Water Reactor Nuclear Power Plant Based on PSASP and Analysis of its Characteristics

Established the mathematical modules of pressurized water reactor (PWR) nuclear power plant (NPP) for the studying of the interactions of the power system and the nuclear power plant after its connecting to system, then set up the user-defined model of PWR NPP using the user-defined modules of the Power System Analysis Software Package (PSASP). Calculate the dynamic traits of PWR NPP without regulating system of reactor and responses to faults in single machine infinite bus system. The results showed the self-stabilization and self-regulation of PWR NPP due to the negative feedbacks of fuel temperature and coolant temperature and the small interaction between power system and NPP if the fault of power system can be eliminated quickly which proved the validity of the model. The model can be used to calculate the influences of the NPP induced by disturbances of voltage or frequency of the system also the influences of the system induced by the change of the output of the NPP after NPP connecting to the power system.