论文部分内容阅读
为了验证中国改进型百万千瓦级(CPR1000)核电站在一回路中等破口失水事故(MLOCA)工况下堆芯冷却监视系统(CCMS)测量的有效性,及定量分析控制系统中反应堆冷却剂泵(简称:主泵)状态的2种判定方法导致的水位计算差异,对CCMS测量原理进行了分析。以RELAP5-3D程序对CPR1000机组进行热工水力建模、使用虚拟数字化控制系统(DCS)模拟其控制逻辑,定量计算了在这2种主泵状态判定方法中CCMS输出水位及其误差,并分析了误差产生的原因。结果表明:2种方案都会引入较大的水位误差,结合状态导向法事故处理程序(SOP)分析,可能使操纵员对堆芯水位判断产生一定的误导。
In order to verify the effectiveness of core cooling monitoring system (CCMS) measurement of China’s improved CPR1000 nuclear power plant in the case of MLOCA and the quantitative analysis of reactor coolant in the control system Pump (referred to as: the main pump) state of the two kinds of judgments caused by water level calculation differences, the CCMS measurement principle was analyzed. The thermal and hydraulic modeling of CPR1000 unit was carried out with RELAP5-3D program, and the control logic was simulated by virtual digital control system (DCS). The CCMS output water level and its error in these two main pump state determination methods were calculated and analyzed quantitatively The reason for the error. The results show that both schemes introduce large water level errors. Combined with SOP analysis, it is possible for operators to mislead the core water level judgment.