论文部分内容阅读
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。
The structural integrity of reactor pressure vessel is one of the key issues to be considered in the operation and life extension of nuclear power plants. In particular, the verification of the structural integrity of reactor pressure vessels under pressure thermal shock (PTS) conditions is of great importance to the safe operation of power plants. In order to verify the structural integrity of the AP1000 reactor pressure vessel, the necessity of the definitive structural integrity analysis of the AP1000 reactor vessel is briefly described and the structural integrity of the pressure vessel under typical PTS transients is evaluated. The analysis and evaluation were carried out by the FAVLoad module in FAVOR, and the module was verified by using the benchmark test IAEA-TECDOC-1627. Finally, the structural integrity of the AP1000 reactor pressure vessel was evaluated. The evaluation results show that the actual RTPTS value at the end of life of the AP1000 reactor pressure vessel is lower than the corresponding limit of the hypothetical PTS transient. The structural integrity of the reactor pressure vessel under typical PTS transients can be guaranteed, as well as the feasibility of using the FAVLoad module to evaluate the deterministic structural integrity of reactor pressure vessels.