摘要
为了更好地分析压水堆发生主蒸汽管道断裂(main steam line break,MSLB)叠加一根蒸汽发生器传热管破裂(steam generator tube repture,SGTR)叠加事故的热工水力过程,用Relap5/mod3.2程序对事故进程进行模拟。比较计算结果与参考电站结果,一回路压力、一次侧向二次侧泄漏流量等主要参数变化趋势一致,安注投入等安全响应的情况基本相同,证明了本次计算的可信性。分析主要参数的变化趋势并解释其变化原因,总结出完整的事件序列和操作员干预的措施。对堆芯水位的计算结果表明:操作员在10min内对事故进行干预情况下堆芯不裸露,反应堆是安全的。
The thermo-hydraulics of a PWR accident with one steam generator tube rupture （SGTR） concurrent with a main steam line break （MSLB） were analyzed using RelapS/mod3.2 program to simulate the accidental advancement. The calculated results agree well with data from an experimental power plant with similar variations in the primary pressure, the primary leakage rate, and other key indicator. The response of the ECCS was also similar to that in the actual plant, which verifies the reliability of the computations. The main parametric variations are analyzed with a summary of the event sequence and the operator response. The results verify that the core is in no danger of becoming uncovered before an operator response in 10 min, which verifies the reactor safety.
出处
《清华大学学报（自然科学版）》
EI
CAS
CSCD
北大核心
2007年第3期373-376,共4页
Journal of Tsinghua University(Science and Technology)
