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    STP824

    Fuel Rod Deformation in LOCA and Severe Core Damage Accidents

    Published: Jan 1984


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    Abstract

    The use of standard creep rate correlations and a burst criterion based on local true stress to evaluate Zircaloy cladding ballooning and burst strain is discussed. Burst strains calculated by this means are shown to follow the trends observed in tubing burst tests. Calculation of the ballooning strains for the Three Mile Island-2 fuel rods, ignoring the effects of oxidation, are discussed.

    Keywords:

    zirconium, zirconium alloys, nuclear fuel cladding, safety, oxidation, deformation, light-water rectors


    Author Information:

    Burman, DL
    Fellow engineer, engineer, advisory engineer, and engineer, Westinghouse Electric Corp., Pittsburgh, Pa.

    Davis, DD
    Fellow engineer, engineer, advisory engineer, and engineer, Westinghouse Electric Corp., Pittsburgh, Pa.

    Hochreiter, LE
    Fellow engineer, engineer, advisory engineer, and engineer, Westinghouse Electric Corp., Pittsburgh, Pa.

    Lutz, RD
    Fellow engineer, engineer, advisory engineer, and engineer, Westinghouse Electric Corp., Pittsburgh, Pa.


    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP34508S


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