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采用美国MST公司核事故仿真软件PCTRAN,对AP1000小破口失水事故进行瞬态曲线分析,仿真结果表明:当发生400 cm2小破口失水事故后,AP1000机组堆芯补水箱和堆芯安注箱水位随反应堆系统压力下降而下降,反应堆系统压力降到13.09 MPa时,触发AP1000机组非能动余热排出系统热交换器导出堆芯余热;当反应堆系统的压力降到1.52MPa时,堆芯水位开始上升;到反应堆系统压力达到0.29 MPa后,压力开始趋于稳定。计算后的反应堆系统压力在数值上与西屋公司用NOTRUMP软件分析的结果大致一样。
The transient state curve analysis of AP1000 small-break water loss accident was carried out by PCTRAN, a nuclear accident simulation software from MST Company in the United States. The simulation results show that when 400 cm2 small-break water loss accident occurs, AP1000 reactor core water supplement tank and reactor core When the reactor system pressure drops to 13.09 MPa, the AP1000 unit passive residual heat removal system heat exchanger is triggered to export the core waste heat. When the reactor system pressure drops to 1.52 MPa, the reactor core water level Began to rise; to the reactor system pressure reached 0.29 MPa, the pressure began to stabilize. The calculated reactor system pressure is numerically the same as Westinghouse’s NOTRUMP software analysis.