反应堆压力容器承压热冲击瞬态载荷与断裂分析

Pressurized thermal shock transient loading and fracture analysis of reactor pressure vessel

为探究堆芯衰变热条件对反应堆承压热冲击(PTS)安全分析的影响,基于带堆芯的ACP1000反应堆压力容器(RPV)模型,通过三维流固耦合传热方法,对小破口冷却剂流失事故(SBLOCA)及稳压器阀门卡开事故两种工况下的PTS瞬态进行数值模拟,通过确定性断裂分析计算裂纹参数,得到了带堆芯衰变热模型的应力强度因子分析结果。结果显示,在不同工况条件下,考虑堆芯衰变热的RPV模型PTS瞬态热载荷较大,过冷瞬态的应力强度因子提高,考虑堆芯热效应能够得到更接近实际PTS工况的分析结果,且堆芯热影响大小与多因素相关。

In order to investigate the influence of decay thermal conditions on the safety analysis of reactor Pressurized Thermal Shock(PTS),based on the ACP1000 reactor pressure vessel(RPV)model with core,the PTS transients under two operating conditions,the small break loss of coolant accident(SBLOCA)and the primary loop stuck open pressurizer accident,were numerically simulated by a 3D fluid-solid coupled heat transfer method,and the stress intensity factor curves under decay heat conditions were obtained by calculating the cracking parameters through deterministic fracture analysis.The results show that under different operating conditions,the PTS transients of the RPV model considering the core decay heat have higher thermal loads,the stress intensity factor of the subcooling transients is increased,and it is considered that the analysis results of core thermal effect closer to actual PTS operating conditions can be obtained,and the magnitude of the core thermal effect is related to multiple factors.