STP681

    Studies on Zircaloy Fuel Clad Ballooning in a Loss-of-Coolant Accident—Results of Burst Tests with Indirectly Heated Fuel Rod Simulators

    Published: Jan 1979


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    Abstract

    Burst tests with indirectly heated fuel rod simulators were performed under cooling and temperature conditions postulated for a loss-of-coolant accident (LOCA) of a pressurized water reactor (PWR). The tests were designed to investigate the ballooning behavior of Zircaloy fuel rod claddings and to determine the resulting coolant channel blockage in a rod bundle.

    The deformation behavior of the Zircaloy cladding tubes was found to be influenced mainly by local effects due to nonuniform temperature distributions. Single rod and bundle tests exhibited large azimuthal and axial temperature differences. This resulted in relatively small and axially limited strains of the Zircaloy cladding tubes and a tolerable coolant channel blockage in the rod bundle.

    Keywords:

    zirconium alloys, nuclear fuel cladding, plastic deformation, cooling, pressurized water reactors, loss-of-coolant accident


    Author Information:

    Erbacher, F
    Section leader and engineers, Kernforschungszentrum Karlsruhe, Institut für Reaktorbauelemente, Projekt Nukleare Sicherheit, Karlsruhe,

    Neitzel, HJ
    Section leader and engineers, Kernforschungszentrum Karlsruhe, Institut für Reaktorbauelemente, Projekt Nukleare Sicherheit, Karlsruhe,

    Wiehr, K
    Section leader and engineers, Kernforschungszentrum Karlsruhe, Institut für Reaktorbauelemente, Projekt Nukleare Sicherheit, Karlsruhe,


    Paper ID: STP36694S

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP36694S


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