United States Nuclear Regulatory Commission - Protecting People and the Environment

Application of Automated Analysis Software to Eddy Current Inspection Data from Steam Generator Tube Bundle Mock-up (NUREG/CR-7217, ANL-11/60)

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Publication Information

Manuscript Completed: January 2012
Date Published: September 2016

Prepared by:
S. Bakhtiari, W.J. Shack and T.W. Elmer
Argonne National Laboratory
Argonne, IL 60439

M. Rossi, NRC Project Manager

NRC Job Code Y6582

Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington DC 20555-0001

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This report documents the results of evaluations of computerized data screening software used for analyzing eddy current data obtained during the inspection of steam generator tubes. The work was performed at Argonne National Laboratory (ANL) as part of on-going activities under the International Steam Generator Tube Integrity Program (ISG-TIP) sponsored by the U.S. Nuclear Regulatory Commission (NRC). Following the initial review of the available literature, a software-based tool widely used by industry for in-service inspection applications was acquired and used to automatically analyze bobbin probe data collected previously from the ANL-NRC steam generator tube bundle mock-up. A subset of that data was initially used to establish data screening parameters. The results of those tests were used to iteratively adjust the data screening parameters to further evaluate their influence on the detection and classification of signals. Alternative configurations of the data screening parameters for different regions of the SG mock-up were further examined. The detection probability and false call rate were evaluated to help determine the influence of selected data screening parameters on the performance of automated data analysis software. The data in each chosen configuration was sorted out using special-purpose algorithms generated at Argonne with standard spreadsheet software. The results of analyses performed on eddy current inspection data from different elevations of the SG mock-up are discussed in this report. Comparisons are made between the detection probability results based on automated analysis with that based on manual analysis of data from a previous round-robin exercise. Some general remarks are finally provided regarding advantages and limitations of conventional automated data analysis programs for inservice inspection of steam generator tubes based on bobbin probe examinations.

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