CPR1000型核电站给水泵事故瞬态分析

Transient Analysis on Failures of Feed Water Pump at CPR1000 Nuclear Power Station

以CPR1000型核电站3×50%电动给水泵为研究对象,采用基于RELAP5和Simulink程序开发的CPR1000数字化仪控系统仿真试验台,详细计算分析了给水泵单泵故障和双重故障对反应堆运行的影响及相应的缓解措施。结果表明,给水泵单泵故障对反应堆运行的影响较小,各相关参数能够很快重回事故前的稳态工况。在给水泵双重故障情况下:初始核功率在75%FP及以下时,不会出现蒸汽发生器(SG)低-低水位;初始核功率高于75%FP、汽机初始负荷在90%FP及以下时,需将汽机负荷阶跃降至50%FP,才不会出现SG低-低水位;汽机初始负荷在90%FP以上时,建议停堆。

Taking 3×50% motor-driven feed water pumps of CPR1000 nuclear power station as research object, and using CPR1000 digital control system simulation platform based on RELAP5 and Simulink codes, the best estimate calculation of effects on reactor operation caused by single or double failures of feed water pump and corresponding mitigation measures were performed. The results show that the effect on reactor operation caused by single failure of feed water pump is small, and the relevant parameters can quickly return to the steady-state condition before the accident. In the case of double faults of feed water pump： When the initial nuclear power is equal or less than 75%FP, the steam generator （SG） will not reach low-low level; when the initial nuclear power is above 75%FP, and the initial turbine load is equal or less than 90%FP, turbine load need step down to 50%FP to avoid SG low-low level; when the initial turbine load is above 90%FP, shutdown of the reactor is proposed.