针对核电站在役期间检查发现的微小裂纹，通常采用核电站在役检查大纲来进行评估实施。对于遵照法系规范设计的电站，一般采用法国核岛设备设计和建造及在役检查协会编制的核电厂核岛机械设备在役检查规则(简称RSE-M，下同)来开展裂纹扩展分析。本文分别基于1997版和2010版RSE-M规范对某堆型核电站典型设备缺陷开展断裂分析，分析发现参考2010版RSE-M规范得到的结果更为精确，能够更为实际的对核电站设备的寿命进行评估，节约电厂运行成本。
For the micro-cracks found during the in-service inspection of nuclear power plants, the nuclear power plant in-service inspection program is usually used for evaluation and implementation. For power stations designed in accordance with the legal system specifications, the crack propagation analysis is generally carried out using the nuclear power plant nuclear island mechanical equipment in-service inspection rules (referred to as RSE-M, the same below) prepared by the French nuclear island equipment design and construction and the in-service inspection association. Based on the 1997 edition and the 2010 edition of the RSE-M specification, this paper conducts fracture analysis on the typical equipment defects of a nuclear power plant. It is found that the results obtained with reference to the 2010 edition of the RSE-M specification are more accurate and can be more practical for the life of nuclear power plant equipment to conduct an assessment to save plant operating costs.
References
[1]
RSEM (1997) In-Service Inspection Rules for the Mechanical Components of PWR Nuclear Islands. 2nd Modification.
[2]
RSEM (2000) In-Service Inspection Rules for the Mechanical Components of PWR Nuclear Islands. 2nd Modification.
[3]
RSEM (2005) In-Service Inspection Rules for the Mechanical Components of PWR Nuclear Islands. 2nd Modification.
[4]
RSEM (2010) In-Service Inspection Rules for the Mechanical Components of PWR Nuclear Islands.
