摘要
在瞬态过程中,当处于承压状态下的反应堆压力容器(RPV)的内表面被快速冷却时,即为承压热冲击(PTS)。由此,反应堆压力容器可能出现贯穿裂纹而失效。为分析PTS事件导致RPV出现裂纹的频率,需要进行概率安全评价(PSA)。通过PSA模型确定可能引起PTS的事件序列,并结合这些序列的热工水力分析结果,为PTS概率断裂力学分析提供支持。
During transient,the inner surface of pressurized reactor pressure vessel（RPV）is cooled quickly,which is termed as pressurized thermal shock（PTS）.So,a flaw may be caused and propagate through the RPV wall,that makes the RPV failure.Probabilistic safety assessment（PSA）is used to analysis the frequency of RPV flaw due to PTS.PSA model finds out the PTS event sequences,combining with the thermal hydraulic analysis, which supports the probabilistic fracture mechanics analysis for PTS.
出处
《核科学与工程》
CSCD
北大核心
2017年第4期521-524,共4页
Nuclear Science and Engineering
基金
基金项目:CAP1400核岛重大设备设计技术研究(2010ZX06002-002)
关键词
承压热冲击
概率安全评价
Pressurized thermal shock
Probabilistic safety assessment
