Results From Pressure and Leak-Rate Testing of Laboratory-Degraded Steam Generator Tubing (NUREG/CR-6789)

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Publication Information

Manuscript Completed: November 2001
Date Published: November 2002

Prepared by:
K. Kasza, S. Majumdar, I. Park,
J. Franklin

Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439

J. Davis, 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 presents experimental results obtained from the pressure and leak-rate testing on laboratory-degraded steam generator (SG) tubes. This work Is part of the NRC sponsored Steam Generator Tube Integrity Program. Two tube test facilities were built to carry out the tests. One is the High-Temperature Pressure and Leak-Rate Test Facility (temperatures up to 343°C [650°F], pressures of up to 21 MPa [3000 psi], and pressurized-water flow rates up to 1520 L/min [400 gpm]) for.conducting tube failure and leak-rate tests under prototypic SG operating conditions. The other is the Room-Temperature High-Pressure Facility (pressures up to 52 MPa [7,500 psi] and flow rates up to 48.4 L/mln 112.8 gpm]) capable of testing at pressures associated with overpressure safety margins. The report includes information on flawed-tube testing protocols for tests with or without Internal bladders, the validity of simple orifice flow models for the prediction of flow rates from flaws, and a large data base containing failure pressures and leak rates for machined and stress corrosion cracking (SCQ) flaws produced In the laboratory.