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    ZHU Zhi-Bin, MA Qiang, CHEN Wen-Hui, DING Bo-Yuan. Eddy Current Data Analysis for Wears of Steam Generator Heat Transfer Tubes in Nuclear Power Station[J]. Nondestructive Testing, 2013, 35(4): 15-17.
    Citation: ZHU Zhi-Bin, MA Qiang, CHEN Wen-Hui, DING Bo-Yuan. Eddy Current Data Analysis for Wears of Steam Generator Heat Transfer Tubes in Nuclear Power Station[J]. Nondestructive Testing, 2013, 35(4): 15-17.

    Eddy Current Data Analysis for Wears of Steam Generator Heat Transfer Tubes in Nuclear Power Station

    • Steam generator tubes will suffer degradation due to mechanical and chemical mechanism during the operation period, which must be tracked using eddy current testing technology. Anti-Vibration(AVB) wear is caused by the friction between the steam generator tubes and AVB structure, which belongs to mechanical mechanism tube degradation and shall lead to the thinning of the tube outer wall. This phenomenon often occurs in the bent pipe section area. This paper uses TEDDY EVA analysis software of Spain to accurately detect the AVB wear damage through the amplitude depth evaluation criterion, and thus to effectively follow-up and monitor the operation status of the pipe.
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