反应堆压力容器超标缺陷评价中几个值得注意的问题

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Nuclear Safety Review on Exceeding Allowable Flaw Treatment of Reactor Pressure Vessel

1. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, 100084, China;
2. Ministry of Environmental Protection, Beijing, 100035, China;
3. Nuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing, 100082, China

摘要: 结合田湾核电站2号机组反应堆压力容器(RPV)、秦山核电二期扩建工程4号机组RPV超标缺陷处理不符合项的安全审查,着重从RPV超标缺陷断裂力学安全评价的评价标准、缺陷特征化、断裂韧性、残余应力取值和承压热冲击等几个方面进行讨论,讨论结果对后续的此类不符合项的处理和安全评价有借鉴意义。
- 反应堆压力容器 /
- 超标缺陷 /
- 安全评价
Abstract: Based on the nuclear safety review on the defect beyond tolerance of Unit 2 reactor pressure vessel of Tianwan NPP and Unit 4 reactor pressure vessel of Qinshan Phase II NPP, to the standards for the safety evaluation of the fracture mechanics of RPV defects beyond tolerance, the defect characterization, the fracture toughness, the selection of residual stress and the thermal shock under load are discussed, in order to be useful for the follow-up of the nuclear safety review.
- Reactor pressure vessel /
- Defect beyond tolerance /
- Nuclear safety review