STP955

    Phase Transformations in Neutron-Irradiated Zircaloys

    Published: Jan 1987


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    Abstract

    Microstructural evolution in Zircaloy-2 and -4 spent-fuel cladding specimens after three years of irradiation in commercial power reactors has been investigated by transmission and high-voltage electron microscopies. Two kinds of precipitates induced by the fastneutron irradiation in the reactors have been identified, that is, Zr3O and cubic-ZrO2 particles approximately 2 to 10 nm in size. By means of specimen tilting and dark-field stereomicroscopy, the bulk nature of the cubic-ZrO2 particles has been shown. The Zr(Fex,Cr1−x)2 and Zr2(Fex,Ni1−x) intermetallic precipitates normally present in the as-fabricated material virtually dissolved in the spent-fuel cladding specimens after a fast-neutron fluence of ∼4 × 1021 n/cm2 in the power reactors. The observed radiation-induced phase transformations are discussed in relation with the currently available understanding of the alloy characteristics.

    Keywords:

    Zircaloys, irradiation, precipitates, stereomicroscopy, brittle failure


    Author Information:

    Chung, HM
    Metallurgist, Argonne National Laboratory, Material Science and Technology Division, Argonne, IL


    Paper ID: STP33851S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP33851S


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