United States Nuclear Regulatory Commission - Protecting People and the Environment

Steam Generator Tube Integrity Program Annual Report: October 1998 – September 1999 (NUREG/CR-6511, Volume 8)

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Publication Information

Manuscript Completed: October 2001
Date Published: July 2002

Prepared by:
D. R. Diercks, S. Bakhtiari, K. E. Kasza, D. S. Kupperman,
S. Majumdar, J. Y. Park, W. J. Shack

Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439

Subcontractors:
*ARES Corporation
851 University Blvd. S.E.
Albuquerque, NM 87106

J. Muscara, NRC Project Manager

Prepared for:
Division of Engineering Technology
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

NRC Job Code W6487

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Abstract

This report summarizes work performed by Argonne National Laboratory on the Steam Generator Tube Integrity Program during the period October 1998 through September 1999. The program is divided into five tasks: (1) Assessment of Inspection Reliability; (2) Research on In-Service-Inspection (ISI) Technology; (3) Research on Degradation Modes and Integrity; (4) Integration of Results, Methodology, and Technical Assessments for Current and Emerging Regulatory Issues; and (5) Program Management. Under Task 1, progress is reported on the assembly of the steam generator tube mock-up, the collection of data for the round robin exercise, and the review of these data. In addition, the effect of a corrosion product on the eddy current signal from a stress corrosion crack is being evaluated, and a technique for profiling cracks based on phase analysis is being developed. Under Task 2, research efforts were associated primarily with multiparameter analysis of eddy current NDE results. Two separate multifrequency mixing procedures are being evaluated, and the application of a signal restoration technique to enhance the spatial resolution of rotating probes is being studied. Under Task 3, laboratory-induced cracking has been produced in a total of ≈450 Alloy 600 tubes. Additional tests have been conducted using the Pressure and Leak-Rate Test Facility on EDM axial notch OD flaws of several different lengths and flaw depth, and the High-Pressure Test Facility has been completed and utilized in initial tests on tubes with OD axial EDM throughwall and part-throughwall notches. Models for predicting the onset of crack growth and for calculating crack opening area and leak rate from a throughwall circumferential crack in a steam generator tube have been developed. In addition, models for predicting the failure of Electrosleeved tubes have been developed. Under Task 4, eddy current and ultrasonic examinations were conducted on test sections with cracks grown at Argonne.

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