Steam Generator Tube Integrity Issues:Pressurization Rate Effects, Failure Maps, Leak Rate Correlation Models, and Leak Rates in Restricted Areas (NUREG/CR-6879, ANL-05/16)

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Publication Information

Manuscript Completed: October 2008
Date Published: July 2009

Prepared by:
S. Majumdar, K. Kasza, S. Bakhtiari, J.Y. Park, J. Oras
J. Franklin, C. Vulyak, Jr., and W.J. Shack
Nuclear Engineering Division
Argonne National Laboratory
9700 South Cass Avenue
Argonne, Illinois 60439

Margaret Stambaugh, NRC Project Manager

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

NRC Job Code Y6582

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Abstract

This report summarizes results obtained under the Third International Steam Generator Tube Integrity Program (ISG-TIP-3). Tests were conducted to determine the effect of pressurization rate on rupture of flawed tubes. Based on analysis and tests, failure maps were developed that delineate ranges of ligament and crack sizes that could be susceptible to ligament rupture and/or unstable burst due to pressure drops of ΔP_NO (normal operation), ΔP_MSLB (main steam-line break), 1.4ΔP_MSLB, and 3ΔP_NO. Tests were conducted to determine the limits of applicability with respect to the through wall crack length and crack tightness of the simple orifice model for predicting leak rates of cracked tubes. Finally, leak rates were calculated for degraded tubes in restricted areas during postulated design-basis and severe accident conditions.