基于RELAP5-3D的全范围模拟机CPR1000反应堆SGTR影响分析

Influence Analyses of CPR1000 PWR SGTR with Full Scope Simulator Based on RELAP5-3D

以全范围模拟机为平台模拟中国改进型百万千瓦级压水堆(CPR1000)堆型核电机组在发生单根传热管断裂事故(SGTR)瞬态,对事故后1.5 h不干预和1.5 h内依照事故规程进行干预分别进行计算,并通过与文献的对比对仿真结果的准确性进行验证,研究主要参数的变化趋势并分析其变化原因,给出完整的事件序列和操作员干预的措施。

This paper researched the behavior of CRP1000 nuclear power plant steam generator tube rupture(SGTR) accident with full scope simulator(FSS).Two different conditions of SGTR,without intervention in 1.5 hours after SGTR and with operator intervention according to operation specification are calculated.Results have been compared with the reference accident analysis report to verify this simulator.Tendency and reasons for the change of important parameters have been studied and analyzed,and the entire incident sequence and operation intervention are given.