STP1175: Irradiation Growth of Zirconium Alloys

    Yang, JC
    China Institute of Atomic Energy, Beijing,

    Ren, JY
    China Institute of Atomic Energy, Beijing,

    Pages: 8    Published: Jan 1994


    Abstract

    Experimental investigation of irradiation growth on annealed Zircaloy-4 and 20% to 50% cold-worked Zr-2.5wt%Nb specimens with stress relief has been carried out. The specimens are irradiated in a heavy water reactor at 610 K to 4.2 x 1024 n/m2 (E > 1.0 MeV). The growth strains increase linearly with fluence. The saturation of growth is not observed for all specimens. The difference of growth behavior between two kinds of Zircaloy-4 tube may be associated with the content of minor alloying elements and impurities that influence the microstructure evolution under irradiation.

    The difference of growth strains of cold-worked Zr-2.5wt%Nb at different temperature of stress relief is related to the grain size and shape and the degree of cold work.

    Keywords:

    zircaloy, irradiation, irradiation growth, texture, neutron fluence, stress relief


    Paper ID: STP23994S

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP23994S


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