堆芯中子注量率测量系统指套管磨损现象分析  

Assessment on Wear of In-Core Flux Thimble in a Typical Pressurized Water Reactor

作　　者：张明乾 黄美良 付月明 禇倩倩 Zhang Mingqian;Huang Meiliang;Fu Yueming;Chu Qianqian(China Nuclear Power Design Company,Ltd.,Shenzhen,Guangdong,518172,China;Nuclear and Radiation Safety Center,MEP,Beijing,100082,China)

机构地区：[1]深圳中广核工程设计有限公司,广东深圳518172 [2]环境保护部核与辐射安全中心,北京100082

出　　处：《核动力工程》2018年第6期96-100,共5页Nuclear Power Engineering

摘　　要：堆芯中子注量率测量系统指套管磨损现象在在役的中国改进型百万千瓦级(1000MW)压水堆核电厂中普遍存在。为深入了解指套管磨损现象,获得指套管磨损的影响因素和在反应堆内的分布规律,为指套管磨损原因分析和结构改进提供指引。对36组通过涡流检查获得的指套管磨损数据进行分析,获得如下结论:指套管磨损程度与对应的堆内构件支承柱、格架板形式存在关系;在反应堆内靠近O°方位区域内的指套管更易发生磨损;电站运行初期,指套管磨损较快,随着电站运行,磨损程度趋于稳定;近年运行的电站在第一次涡流检测时获得的指套管磨损现象更严重。The wear damage of the in-core flux thimble was often reported from the advanced pressurized water reactor (1000MW)in China.In order to improve our understanding of the wear phenomena and obtain the factors which influence the result of wear,36 groups of wear data for the in-core flux thimble are collected from the nuclear power plants in service,which are measured by eddy current examination during the plant outage.The main conclusions obtained on the basis of the analysis about the wear data are as follows:The wear rate of the in-core flux thimble is directly related with the type of the support column and the tie plate.In-core flux thimbles located closely at the area of the zero azimuth in the reactor could be more subjected to worse wear.The wear defect-growing trend increases significantly at the initial stage of the plant operation,and moves toward stabilization with it.The wear damage reported from the plants constructed in recent years is gradually deteriorating.

关 键 词：指套管 堆内构件 磨损 

分 类 号：TL386[核科学技术—核技术及应用]