CPR1000压水堆安全壳实时仿真模型研究

Real-time dynamic model for the containment of a CPR1000 PWR nuclear power plant training simulator

为了研究CPR1000压水堆核电站安全壳在严重事故下的动态特性,通过对安全壳控制体节点的划分以及合理的机理分析和简化,建立了两相、多组分、热力学非平衡的多节点安全壳实时仿真模型,并运用于某CPR100压水堆核电站全范围模拟机,将计算结果与MEFRA-1工程分析程序进行了对比。模拟机验收结果表明:所建模型能够正确地模拟反应堆冷却剂系统失水事故(LOCA)、蒸汽管道泄漏事故等情况下,安全壳内的压力和大气温度、地坑水位以及温度等参数的动态特性。

A multi-component, two-phase, non-thermal equilibrium, multi-node containment model was developed for a CPR1000 full scope training simulator. The simulation results were compared with those of the MEFRA-1 engineering analysis program. The containment model was also fully analyzed by experts during the simulator acceptance test. The results show that the established model can correctly reflect the dynamic characteristics of the containment in accidents, including the loss of coolant accident （LOCA）, steam pipe leakage, and so on.