反应堆压力容器役致裂纹验收标准制定方法研究OA
Establishment Method of Service Induced Crack Acceptance Standard for Reactor Pressure Vessel
为满足压水堆核电厂反应堆压力容器(RPV)在役检查发现裂纹(役致裂纹)的快速评估需求,需进行役致裂纹验收标准制定方法研究并制定RPV役致裂纹的验收标准.本文分析了美国电力研究协会(EPRI)提出的役致裂纹验收标准制定原则和制定方法,以RPV设计阶段防断裂分析的假想裂纹为基准裂纹,结合役致裂纹验收标准制定的安全准则,提出了一种基于设计假想裂纹和设计安全系数的役致裂纹验收标准制定力学分析方法;应用本文提出的方法对RPV筒体制定的役致裂纹验收标准与ASME给出的验收标准基本接近.本文提出的役致裂纹验收标准制定力学分析方法也适用于其他核电承压设备.
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.
侯帆;王大胜;段远刚;向文欣;金挺;祁磊;刘攀
中广核核电运营有限公司,深圳 518172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台山核电合营有限公司,台山 529200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台山核电合营有限公司,台山 529200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
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反应堆压力容器役致裂纹验收标准安全准则
reactor pressure vesselservice-induced crackacceptance standardsafety criterion
《核安全》 2026 (2)
60-65,6
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