AP1000反应堆压力容器承压热冲击下结构完整性分析  

Structure integrity evaluation of AP1000 RPV under PTS

作　　者：王东辉 张亚平 钟志民 李锴 张静 

机构地区：[1]国核电站运行服务技术公司,上海200233

出　　处：《核技术》2013年第4期151-158,共8页Nuclear Techniques

基　　金：国家大型先进压水堆核电站重大专项(2011ZX06001-003)资助

摘　　要：反应堆压力容器结构完整性是核电厂运行及延寿时需重点关注的问题之一。特别是承压热冲击(PTS)工况下反应堆压力容器结构完整性的验证工作对电厂能否安全运行有重要意义。为验证AP1000反应堆压力容器的结构完整性,本文简要阐述了AP1000反应堆压力容器进行确定性结构完整性分析的必要性,并对压力容器在典型PTS瞬态下的结构完整性进行了评价。分析评价采用概率断裂力学软件FAVOR中的FAVLoad模块进行,并应用IAEA-TECDOC-1627中的基准考题对该模块进行了验证,最后对AP1000反应堆压力容器进行了确定性结构完整性评价。评价结果表明,AP1000反应堆压力容器寿期末实际RTPTS值低于假想PTS瞬态对应的限值。反应堆压力容器在典型PTS瞬态下的结构完整性可以保证,同时也说明采用FAVLoad模块进行反应堆压力容器确定性结构完整性评价的方法可行。Background： The structure integrity of Reactor Pressure Vessel （RPV） is one of the main concerns related to the safe operation and plant-life extension issues for nuclear power plant. It is very important for the operation safety of nuclear power plant to verify the structure integrity of RPV under Pressurized Thermal Shock （PTS）. Purpose： To verify the structure integrity of AP1000 RPV, the necessary of structure integrity evaluation with deterministic method is discussed in this article and the evaluations for AP1000 RPV are performed. Methods： FAVLoad, which is the fracture mechanical analysis module in FAVOR, is applied in the evaluations. The benchmarks from IAEA-TECDOC-1627 are analyzed for verification. At last, the deterministic structure integrity analysis and evaluation of AP1000 RPV are performed. Results： The RTpTs for AP1000 RPV is lower than the limit under the assuming PTS transients obtained in the analysis. Conclusions： The results show that the integrity of AP1000 RPV can be maintained, and the PTS analysis method with FAVLoad for RPV is feasible.

关 键 词：AP1000 反应堆压力容器(RPV) PTS 结构完整性 

分 类 号：TL351.6[核科学技术—核技术及应用]