压水堆核电站反应堆压力容器顶盖在役检查

详细信息

In-service Inspection of Pressurized Water Reactor Pressure Vessel Head

摘要: 介绍了压水堆核电站反应堆压力容器顶盖劣化和失效案例，以及核电机组的反应堆压力容器顶盖结构。结合案例分析了当前反应堆压力容器顶盖在役检查要求，阐述了满足在役检查要求的反应堆压力容器顶盖在役检查技术，分析了顶盖在役检查技术中表面检验和体积检验的技术难点以及解决措施。提出对我国压水堆反应堆压力容器顶盖实施定期在役检查的建议。
- 压水堆 /
- 核电站 /
- 反应堆压力容器 /
- 顶盖 /
- 在役检查
Abstract: This paper mainly introduces the cases of degradation and failure of reactor pressure vessel head (RPVH) in Pressurized Water Reactor (PWR) nuclear power plants, and the structure of RPVH of nuclear power units. It analyzed the current in-service inspection (ISI) requirements of RPVH, described RPVH ISI technology meeting the ISI requirements, and finally analyzed the technical difficult points of surface inspection and volume inspection and solutions. It proposed suggestions on periodical ISI for RPVH of domestic PWRs.
- Pressurized water reactor /
- Nuclear power plant /
- Reactor pressure vessel /
- Head /
- ISI