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    STP905

    Variable Flaw Shape Analysis for a Reactor Vessel under Pressurized Thermal Shock Loading

    Published: 0


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    Abstract

    A study has been conducted to characterize the response of semi-elliptic surface flaws to thermal shock conditions which can result from safety injection actuation in nuclear reactor vessels. A methodology was developed to predict the behavior of a flaw during sample pressurized thermal shock events. The effects of a number of key variables on the flaw propagation were studied, including (1) fracture toughness of the material and its gradient through the thickness, (2) irradiation effects, (3) effects of warm prestressing, and (4) effects of the stainless steel cladding.

    The results of these studies show that under thermal shock loading conditions the flaw always tends to elongate along the vessel inside surface from the initial aspect ratio. However, the flaw shape always remains finite rather than becoming continuously long, as has often been assumed in earlier analyses. The final shape and size of the flaws were found to be rather strongly dependent on the effects of warm prestressing and the distribution of neutron flux.

    The improved methodology results in a more accurate and more realistic treatment of flaw shape changes during thermal shock events and provides the potential for quantifying additional margins for reactor vessel integrity analyses.

    Keywords:

    flaw shape, stress intensity factor, fracture toughness, crack initiation, crack arrest, thermal shock loading, warm prestressing, virtual crack extension (VCE) method


    Author Information:

    Yang, CY
    Westinghouse Electric Corporation, Pittsburgh, PA

    Bamford, WH
    Westinghouse Electric Corporation, Pittsburgh, PA


    Committee/Subcommittee: E08.04

    DOI: 10.1520/STP17387S