基于^(137)Cs、^(85)Kr的燃料元件包壳破损检测系统研制  

Development of Detection System for Fuel Element Cladding Damage Based on ^(137)Cs and ^(85)Kr Nuclides

作　　者：谢波[1] 曾勇[1] 张宏祥[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》2015年第2期55-57,共3页Nuclear Power Engineering

摘　　要：针对停堆时间在4个月以上、不具备脱水条件而又不能采用常规方法检测其包壳是否破损的燃料元件,研制一种检测系统,利用高温水加热燃料元件使放射性核素向外释放,施加压力加速放射性核素释放,通过收集并检测137Cs和85Kr含量来确定燃料元件是否破损。应用结果表明,系统可以在不脱水状态下完成燃料元件包壳的破损检测,具有检测方便、快捷、准确的特点。A detect system was developed for the fuel elements with shutdown of more than 4 months and that can not be taken out from water and tested for the damage of fuel element cladding. The high temperature water is used by the system to heat the fuel element to release the radionuclide, and pressure changes are applied to accelerate the radionuclide release, and then the content of 137 Cs and 85 Kr is collected and detected to determine whether the fuel element is damaged. The results show that the system can conduct the damage detection of fuel element cladding without taking the fuel out from water, and has the characteristics of convenient, fast and accurate.

关 键 词：燃料元件 包壳破损 检测 不脱水状态 

分 类 号：TL352.27[核科学技术—核技术及应用]