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Depth-Sizing Technique for Crack Indications in Steam Generator Tubing  

Cho, Chan-Hee (Korea Electric Power Research Institute)
Lee, Hee-Jong (Korea Electric Power Research Institute)
Kim, Hong-Deok (Korea Electric Power Research Institute)
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Abstract
The nuclear power plants have been safely operated by plugging the steam generator tubes which have the crack indications. Tube rupture events can occur if analysts fail to detect crack indications during in-service inspection. There are various types of crack indication in steam generator tubes and they have been detected by the eddy current test. The integrity assessment should be performed using the crack-sizing results from eddy current data when the crack indication is detected. However, it is not easy to evaluate the crack-depth precisely and consistently due to the complexity of the methods. The current crack-sizing methods were reviewed in this paper and the suitable ones were selected through the laboratory tests. The retired steam generators of Kori Unit 1 were used for this study. The round robin tests by the domestic qualified analysts were carried out and the statistical models were introduced to establish the appropriate depth-sizing techniques. It is expected that the proposed techniques in this study can be utilized in the Steam Generator Management Program.
Keywords
Crack Depth Sizing; Eddy Current Data; Steam Generator Tube;
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