Thermal hydraulic simulations of a PWR nuclear power plant

Abstract

This research presents simulation analyses of steady state, station blackout, and loss of coolant accident thermal hydraulic conditions. The plant is a PWR type with output of about 1000 MWe. The simulations are performed by using RELAP and PCTran codes to develop a model of this PWR which could simulate its primary system, with good accuracy in cases of steady state, station blackout, and loss of coolant accidents. The modelled core temperature distribution, pressure, coolant mass flow inlet and outlet temperatures of the reactor, and other parameters proved to be in good agreement with reference data. These simulations verify the efficiency of management procedures in ensuring that the auxiliary cooling systems can cool the reactor core during accident conditions. The importance of the auxiliary system during the accident conditions is accredited. The developed RELAP and PCTran models are capable of reproducing the thermal hydraulic behaviour of the PWR.