1E级安全壳内用电动机鉴定的核安全审查  

Nuclear Safety Review for Qualification of Class 1E Motor inside Containment for Nuclear Power Stations

作　　者：李世欣[1] 毋琦[1] 张云波[1] 吴彩霞[1] 

机构地区：[1]环境保护部核与辐射安全中心,北京100082

出　　处：《核动力工程》2013年第4期117-120,共4页Nuclear Power Engineering

摘　　要：对压水堆核电厂1E级安全壳内电动机的鉴定过程和鉴定文件进行审查,要求对鉴定试验结果与标准法规的符合性以及与安全壳内环境要求的一致性做出评价。首先介绍1E级安全壳内用电动机的老化试验、设计基准事故试验等主要鉴定试验,对随后审查过程中遇到的典型问题进行分析,并将IEEE 334与RCC-E两套标准进行对比探讨。In nuclear power plants with pressurized water reactors, the review for class 1E motor inside containment qualification process and documents is an important aspect of nuclear safety equipment review, and the reviewers should make evaluations for the qualification test results in terms of the compliance with standard and regulation, and the consistency with inside containment environment. Firstly, this paper introduces the qualification test of class 1E motor inside containment for nuclear power generating stations, such as aging test and design-basis-event test. Second, there is a discussion about typical problems of review. At last, comparison of IEEE334 with RCC-E is conducted and explored.

关 键 词：核安全 电动机 鉴定试验 老化试验 LOCA试验 

分 类 号：TM306[电气工程—电机] TM623