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核电厂反应堆压力容器接管内圆角增强型目视检验技术研究

Research on enhanced vis ual inspection technology of reactor pressure vessels nozzle inner radius in nuclear power plant
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摘要 核电厂需要定期对核岛关键设备如反应堆压力容器接管内圆角区域进行无损检验,从而发现可能存在的缺陷。ASME规范要求对接管内圆角区域实施超声检验,但由于接管内圆角区域结构复杂,且沿周向不断变化,超声检测实施难度较大,检测效率较低,按传统的方式对该区域实施超声检测困难较大。根据美国联邦法规10CFR50对ASME规范的补充要求规定:可采用高灵敏度的目视检验技术来代替超声检验执行容器接管内圆角区域的无损检验。本文结合法规的相关要求,介绍了反应堆压力容器接管内圆角增强型目视检验技术,并结合接管内圆角增强型目视检验检验系统开发的试验研究情况,得出使用特定的检验技术和检验系统,可满足反应堆压力容器接管内圆角检查的需求。 Nuclear power plants need to conduct regular non-destructive testing of the key island nuclear equipment, such as reactor pressure vessel nozzle inner radius, to identify possible defects. The ASME Code requires that ultrasonic testing be performed on the nozzle inner radius area but due to the complicated structure of the nozzle inner radius area and varying circumferences, it is more difficult to perform ultrasonic testing and lower the detection efficiency. Ultrasound is performed on the area in a conventional manner testing is more difficult. According to the supplementary requirements of the US federal regulation 10CFR50 on ASME specification, the non-destructive testing of the nozzle inner radius area should be replaced by a high-sensitivity visual inspection technique. Combining with the requirements of the relevant laws and regulations, this paper introduces the enhanced visual inspection technique of reactor pressure vessel nozzle inner radius, and combined with the experimental research on the development of enhanced visual inspection and inspection system to nozzle inner radius, it is concluded that the use of specific inspection technique and Inspection system to meet the needs of reactor pressure vessel nozzle inner radius inspection.
作者 王羽翀 刘绪 吴化峰 WANG Yu-Chong;LIU Xu;WU Hua-feng
出处 《科技视界》 2018年第8期152-154,共3页 Science & Technology Vision
关键词 核电厂 反应堆压力容器 接管内圆角 增强型目视检验 Nuclear power plant Reactor pressure vessels Nozzle inner radius Enhanced visual inspection
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