The calculated results show that core melt progression is fast and most of the core material melt and relocated to the lower plenum.
结果表明,压水堆发生大破口失水事故时,堆芯熔化进程较快,大量堆芯材料熔化并坍塌至下腔室,反应堆压力容器下封头失效较早,且主回路冷段破口比热段破口更为严重。
In order to predict the in-vessel core melt progression accurately and provide probabilistic safety assessment(PSA) level 2 with the reliable initialization conditions,the creep rupture failure of primary loops pressure boundary was taken into account in code calculation.
为准确预测压力容器内堆芯熔化的进程,为二级概率安全评价提供可信的初始条件,计算中考虑了一回路压力边界的蠕变破裂失效,并评价了人为干预对堆芯熔化进程及事故后果的影响。
In order to predict the in-vessel core melt progression accurately and provide PSA-2 with the reliable initialization conditions,the creep rupture failure of primary loops pressure boundary is taken into account in code calculation.
为准确预测压力容器内堆芯熔化的进程,给二级PSA提供可信的初始条件,计算中考虑了一回路压力边界的蠕变破裂失效,并评价了人为干预对堆芯熔化进程及事故后果的影响。
