STP969: Review of Pressurized-Water-Reactor-Related Thermal Shock Studies

    Cheverton, RD
    Senior development specialist, Oak Ridge National Laboratory, Oak Ridge, TN

    Iskander, SK
    Engineering specialist and computing specialist, Computing and Telecommunications Division, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN

    Ball, DG
    Engineering specialist and computing specialist, Computing and Telecommunications Division, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN

    Pages: 15    Published: Jan 1988


    Abstract

    Flaw behavior trends associated with pressurized thermal shock (PTS) loading of pressurized water reactor (PWR) pressure vessels have been under investigation at Oak Ridge National Laboratory (ORNL) for approximately twelve years. During that time, eight thermal shock experiments with thick-walled steel cylinders were conducted as a part of the investigations. These experiments demonstrated, in good agreement with linear elastic fracture mechanics (LEFM), crack initiation and arrest, a series of initiation/arrest events with deep penetration of the wall, long crack jumps without significant dynamic effects at arrest, arrest in a rising stress-intensity-factor (KI) field, extensive surface extension of an initially short and shallow flaw, and warm prestressing with KI ⩽ 0. This information was used in the development of a fracture mechanics model that is being used extensively in the evaluation of the PTS issue.

    Keywords:

    reactor pressure vessels, thermal shock, thermal shock experiments, pressurized thermal shock, fracture mechanics, pressurized water reactors


    Paper ID: STP33104S

    Committee/Subcommittee: E08.08

    DOI: 10.1520/STP33104S


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