STP1245: Corrosion Performance of New Zircaloy-2-Based Alloys

    Rudling, P
    Specialist and manager, ABB Atom, Västerås,

    Mikes-Lindbäck, M
    Specialist and manager, ABB Atom, Västerås,

    Lethinen, B
    Research metallurgist, Institute of Metals Research, Stockholm,

    Andrén, H-O
    Associate professors, Chalmers University of Technology, Göteborg,

    Stiller, K
    Associate professors, Chalmers University of Technology, Göteborg,

    Pages: 16    Published: Jan 1994


    Abstract

    A material development project was initiated to develop a new zirconium alloy, outside the ASTM specifications for Zircaloy-2 and Zircaloy-4, with optimized hydriding and corrosion properties for both boiling water reactors and pressurized water reactors. A number of different alloys were manufactured. These alloys were long-term corrosion tested in autoclaves at 400°C in steam. Also, a 520°C/24 h steam test was carried out. The zirconium metal microstructure and the chemistry of precipitates were characterized by analytical electron microscopy. The metal matrix chemistry was determined by atom probe analysis. The paper describes the correlations between corrosion material performance and zirconium alloy microstructure.

    Keywords:

    zirconium alloys, zirconium, nuclear materials, nuclear applications, radiation effects, zirconium alloy corrosion, zirconium alloy matrix, second-phase particles


    Paper ID: STP15211S

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP15211S


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