一重技术
一重技術
일중기술
CFHI TECHNOLOGY
2013年
1期
58-61
,共4页
核电%压力容器%断裂%有限元
覈電%壓力容器%斷裂%有限元
핵전%압력용기%단렬%유한원
nuclear power%pressure vessel%fracture%finite element
依据反应堆压力容器A级和B级载荷工况对AP1000核电站反应堆压力容器下筒体及下封头进行分析计算.按照ASME第Ⅲ卷附录G的要求,对其结构进行脆性断裂分析与评定.为核电反应堆压力容器防断裂分析设计计算奠定基础.
依據反應堆壓力容器A級和B級載荷工況對AP1000覈電站反應堆壓力容器下筒體及下封頭進行分析計算.按照ASME第Ⅲ捲附錄G的要求,對其結構進行脆性斷裂分析與評定.為覈電反應堆壓力容器防斷裂分析設計計算奠定基礎.
의거반응퇴압력용기A급화B급재하공황대AP1000핵전참반응퇴압력용기하통체급하봉두진행분석계산.안조ASME제Ⅲ권부록G적요구,대기결구진행취성단렬분석여평정.위핵전반응퇴압력용기방단렬분석설계계산전정기출.
Analysis and calculation are performed on the bottom shell and bottom dome of AP1000 NPR pressure vessels in consideration of A class and B class load conditions of NPR pressure vessels. As per the requirement specified in ASME Section III Appendix G, brittle fracture analysis and evaluation are made on the structure, which paves the foundation for the fracture protection analysis and design calculation of NPR pressure vessels.
