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    STP1597

    Mechanistic Understanding of Zirconium Alloy Fuel Cladding Performance

    Published: 2018


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    Abstract

    A review is presented of work performed in our group over the years in the areas of radiation damage, corrosion, hydrogen pickup, hydriding, and the mechanical behavior of zirconium alloy nuclear fuel cladding with the goal of developing a greater mechanistic understanding of cladding performance in service.

    Keywords:

    zirconium, cladding, fuel performance, radiation damage, corrosion, hydriding, hydrogen pickup, mechanical properties


    Author Information:

    Motta, Arthur T.
    Pennsylvania State University, Dept. of Mechanical and Nuclear Engineering, University Park, PA


    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP159720160095