基于风险的反应堆压力容器压力-温度限值曲线适用性分析  

Applicability analysis of risk-based pressure-temperature limit curve of reactor pressure vessel

作　　者：王东辉[1] 张亚平[1] 李锴[1] 李国健 WANG Donghui;ZHANG Yaping;LI Kai;LI Guojian(State Nuclear Power Plant Service Company,Shanghai 200233,China)

机构地区：[1]国核电站运行服务技术有限公司,上海200233

出　　处：《压力容器》2022年第3期40-47,共8页Pressure Vessel Technology

基　　金：国家科技重大专项资助项目(2019ZX06005002)。

摘　　要：ASME规范和美国联邦法规规定了反应堆压力容器在正常启、停堆过程中的压力和温度限值。采用反应堆压力容器失效概率分析软件FAVOR,对RPV在基于风险的极限降温工况下的容器失效概率(CPF)进行了评价。结果表明,容器在极限降温工况下的失效概率与降温速率、堆焊层厚度和参考温度ART值相关。容器内表面贯穿堆焊层浅裂纹的存在可能导致容器失效概率超出ASMEⅪ卷附录G-2216制定时所基于的允许值(失效概率1×10^(-6)/a)。国内反应堆压力容器材料在使用基于风险的压力-温度限值曲线时,系统降温速率应限制在53℃/h范围内。通过更接近实际降温情况的分析过程可以看出,国内反应堆压力容器在寿期内具有足够裕量来保证其结构完整性。The startup and shutdown pressure-temperature(P-T)limits for reactor pressure vessel(RPV)are specified in ASME code and the U.S.code of Federal Regulations.The FAVOR software was used to evaluate the conditional failure probability(CPF)of reactor pressure vessel under risk-based extreme cooling condition.The results show that the CPF of RPV under extreme cooling condition is related to cooling rate,clad thickness and reference temperature of irradiation embrittlement(ART).The presence of inner shallow cracks through the cladding may cause the failure probability of the vessel to exceed the allowable value failure probability 1×10^(-6)/a,which was used in developing ASME Appendix G-2216.When using the risk-based pressure-temperature limit curve for domestic reactor pressure vessel materials,the system cooling rate should be limited to 53℃/h.It can be seen from the analysis closer to an actual cooling situation that the domestic reactor pressure vessel has sufficient margin to ensure its structural integrity within its service life.

关 键 词：反应堆压力容器 概率断裂力学 失效概率 降温速率 堆焊层浅裂纹 

分 类 号：TH49[机械工程—机械制造及自动化] TL351.6[核科学技术—核技术及应用]