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Filtering by: Subject Zirconium alloys -- Oxidation Remove constraint Subject: Zirconium alloys -- Oxidation Academic Affiliation Nuclear Engineering Remove constraint Academic Affiliation: Nuclear Engineering

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  • Oxidation of Zircaloy-4 in pressurized water reactor conditions

    Creator:
    VanWinkle, James A.
    Abstract:
    A study of the oxidation of zircaloy in reactor environments has been undertaken with the goal of characterizing of the Thermal Gradient Test Facility (TGTF) at Teledyne Wah Chang, Albany. A set of oxidation models is presented from the literature, as well as an extensive database of published oxidation test...
    Resource Type:
    Masters Thesis
    Full Text:
    Jurisch Dollins and Jurisch [7], created a model for oxidation of Zirconium-based alloys based on the

  • A model for waterside oxidation of zircaloy fuel cladding in pressurized water reactors

    Creator:
    Almarshad, Abdullah I. A.
    Abstract:
    A model has been developed to predict the long-term oxidation rate of Zircaloy-4 for ex-reactor (autoclave) and in-reactor (PWR) environments and operating conditions. A computer program has been written to solve the oxygen diffusion equation by employing a fully implicit finite difference method for a one dimensional cylindrical geometry. The...
    Resource Type:
    Dissertation
    Full Text:
    The influence of the alloy surface preparation on the oxidation of 0.5 wt% binaries. 28 2.7 Static