〈기술논문〉 설계기준 초과 과도조건을 가정한 한국 표준형 원전 가압기 밀림노즐 구조건전성에 관한 연구

Out-of-Limit Transients due to thermal stratification are discovered in the pressurizer of the nuclear power plants supplied by Westinghouse. The occurring of out-of-limit transients are not reported in the pressurizer of OPR1000. However, the occurring of out-of-limit transients are assumed for the pressurizer of OPR1000 and are evaluated for the pressurizer surge nozzle structural integrity. The evaluation results show that the ASME Code requirements are met even though out-of-limit transients are considered additionally.