反应堆中子通量测量系统指套管微振磨损长度的测量

详细信息

Measurement of Thimble Tube Fretting Wear Length of Nuclear Reactor Neutron Flux Measuring System

摘要: 简述了CPR1000型核电站堆芯中子通量测量指套管的微振磨损机理，针对支撑处常见的微振磨损，使用涡流方法对其磨损长度进行了精确测量。对主要影响测量结果的线圈响应范围进行了分析和计算，结果表明：精确的外壁磨损长度测量结果为电站对指套管的设计和后期跟踪维护提供了重要参考。
- 指套管 /
- 微振磨损 /
- 涡流检测 /
- 长度测量
Abstract: In this paper, the fretting wear mechanism of the thimble tube of neutron flux measurement in the core of the CPR1000 nuclear power plant is briefly described. For the common fretting wear at the support, an accurate measurement of the wear length using the eddy current method is investigated. The coil response range that mainly affects the measurement results is analyzed and calculated. Accurate outer wall wear length measurement results provide an important reference for the design of the casing and the follow-up maintenance.
- thimble tube /
- fretting wear /
- eddy current inspection /
- length measurement