New version of performance demonstration program for steam generator tubing analysts

被引:0
|
作者
Chan Hee Cho
Hee Jong Lee
Min Woo Nam
Hyun Ju Yoo
Sung-Yull Hong
机构
[1] Central Research Institute,Korea Hydro & Nuclear Power Co., Ltd.
[2] Yeungnam University,School of Mechanical Engineering, College of Engineering
来源
Journal of Mechanical Science and Technology | 2013年 / 27卷
关键词
Eddy current test; Non-destructive examination; Performance demonstration; Steam generator;
D O I
暂无
中图分类号
学科分类号
摘要
The reliability and performance of steam generators (SGs) are serious concerns in the operation of nuclear power plants. In particular, SG tubing is subject to a variety of degradation processes that can lead to potential leakage or rupture. To prevent a plant shutdown from this kind of event, the integrity of SG tubing should be periodically determined. The eddy current test is widely used for the inspection of SG tubing during in-service inspection. For the evaluation of eddy current data, analysts are required to have the Level II or greater qualification based on the american society for nondestructive testing (ASNT) standard. In addition, analysts evaluating eddy current data obtained from SG tubing are required to have a qualification of performance demonstration. The performance demonstration program in Korea has existed since 2004 and uses the qualified data analyst (QDA) program developed by the electric power research institute (EPRI). Recently, the QDA program was updated by EPRI. The updated QDA program has been in effect for SG tubing analysts in Korea since 2010. In this paper, we describe the performance demonstration program, the degradation mechanisms, and the inspection techniques for SG tubing in nuclear power plants.
引用
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页码:679 / 683
页数:4
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