核安全2026，Vol.25Issue(2)：60-65,6.
反应堆压力容器役致裂纹验收标准制定方法研究
Establishment Method of Service Induced Crack Acceptance Standard for Reactor Pressure Vessel
侯帆 1王大胜 2段远刚 2向文欣 3金挺 2祁磊 3刘攀2
作者信息
- 1. 中广核核电运营有限公司,深圳 518172
- 2. 核电安全技术与装备全国重点实验室,中广核工程有限公司,深圳 518172
- 3. 台山核电合营有限公司,台山 529200
- 折叠
摘要
Abstract
It is necessary to formulate the acceptance standard of service induced cracks for Pressurized Water Reactor Nuclear Power Plant reactor pressure vessel(RPV)to meet the needs of rapid assessment for cracks found during the in-service inspection.First,the formulation principle and method of service induced crack acceptance standard proposed by the Electric Power Research Institute(EPRI)are studied and discussed.Subsequently,taking the postulated crack in the fracture resistance analysis of RPV design stage as the benchmark crack,combined with the safety margin of the service induced crack acceptance standard,a mechanical analysis method for establishing acceptance standard for service-induced cracks is proposed based on the design benchmark crack and design safety factor.The service induced crack acceptance standard for RPV components is formulated using the method proposed in this paper,and the results of the developed acceptance standard for service induced crack are basically close to that in ASME code.The establishment method of service induced crack acceptance standard proposed in this paper is also applicable to other nuclear power pressure equipment.关键词
反应堆压力容器/役致裂纹/验收标准/安全准则Key words
reactor pressure vessel/service-induced crack/acceptance standard/safety criterion分类
机械制造引用本文复制引用
侯帆,王大胜,段远刚,向文欣,金挺,祁磊,刘攀..反应堆压力容器役致裂纹验收标准制定方法研究[J].核安全,2026,25(2):60-65,6.
