基于CIVA仿真核电站传热管涡流检测参数的选择  

Choice of Eddy Current Testing Parameters Used in Nuclear Power Steam Generator Tube Based on CIVA Numerical Simulation

作　　者：孙大朋[1] 李冬[1] 刘彦明[1] 杨力[1] 孙永铎[2] 黎为[1] 

机构地区：[1]中国核动力研究设计院核燃料元件及材料研究所无损检测研究室,成都610041 [2]中国核动力研究设计院应堆燃料及材料重点实验室,成都610041

出　　处：《四川兵工学报》2013年第12期91-95,共5页Journal of Sichuan Ordnance

摘　　要：利用CIVA软件平台,采用内穿式差动Bobbin线圈对核电站蒸汽发生器传热管涡流检测进行数值模拟;对传热管内外壁缺陷数值模拟,确定检测时的最佳频率,并与理论计算值进行对比;数值模拟差动式探头2线圈之间间隔大小L、线圈宽度b和周向槽缺陷宽度l对检测结果的影响;利用上述CIVA数值模拟的结果分析相应的变化规律,为应用差动Bobbin线圈对核电用传热管进行涡流检测时线圈参数的选择提供了重要的理论参考依据和实用价值。CIVA simulation software platform was used to study the eddy current testing of the steam gener-ator tube for nuclear power plant with the differential bobbin coil. With numerical simulation, the optimal frequency of detection of the inner and outer walls of the SG tube defects were determined and the theoreti-cal values were compared. The interval size between the probe coil, the coil width and the circumferential groove defect width were used to study the influence on the detect results. In order to find the correspond-ing orderliness, the numerical simulation result from CIVA is used to analyze, which can supply a very im-portant theoretical significance and practicality for eddy current testing used by differential bobbin coil in nuclear power plant.

关 键 词：涡流检测 CIVA数值模拟 差动线圈 SG传热管 

分 类 号：TM623[电气工程—电力系统及自动化]