Effect of Parameter Variation of Reactor Coolant Pump on Loss of Coolant Accident Consequence

In this paper, the analyses were carried out on Ling’ao nuclear power station phaseⅡ to study the consequence of the loss of coolant accident when the homologous characteristic curves and free volumes of the reactor coolant pump changed. Two different pumps used in the analysis were 100D（employed on Ling’ao nuclear power station phaseⅡ） and ANDRITZ. The thermal characteristics in the large break LOCA accident were analyzed using CATHRE GB and CONPATE4, and the reactor coolant system hydraulics load during blow-down phase of LOCA accident was analyzed using ATHIS and FORCET. The calculated results show that the homologous characteristic curves have great effect on the thermal characteristics of reactor core during the reflood phase of the large break LOCA accident. The maximum cladding surface temperatures are quite different when the pump’s homologous characteristic curves change. On the other hand, the pump’s free volume changing results in the variation of the LOCA rarefaction wave propagation, and therefore, the reactor coolant system hydraulic load in LOCA accident would be different.