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    Irradiation-Induced Growth and Microstructure of Recrystallized, Cold Worked and Quenched Zircaloy-2, NSF, and E635 Alloys

    Published: 01 January 2009

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    This paper is devoted to the study of the effect of the texture, phase composition, and microstructure on the irradiation-induced growth strain (GS) of zirconium-based alloys. GS measurements and TEM microstructural examinations were performed on Zry-2, NSF, and E635 samples in the recrystallized, beta quenched and cold-worked (CW) conditions. The samples were irradiated in the BOR-60 reactor in the temperature range of 315–325°C up to a neutron fluence level of 1.1 × 1026 n/m2 (E>1MeV), i.e., up to a damage dose of 23 dpa. Growth strains of NSF and E635 alloys in all states and in the longitudinal and transverse directions are lower as compared to those of Zry-2, and do not exceed 0.2 % even at the maximum fluence level. As for recrystallized Zry-2, the GS kinetics are characterized by the appearance of the accelerated growth stage. A combination of a certain amount of Nb, Fe, and Sn in the matrix content plays a key role in GS kinetics. The higher the degree of CW, the higher the irradiation growth but its rate of increase with increasing fluence is different for alloys of different compositions. The maximum GS, reaching 0.72 %, is observed in the 20 % CW Zry-2 samples. Texture, along with the alloy composition, is one of the main GS-determining factors. Irradiation growth of the transversal samples is lower as compared to the longitudinal ones because of texture. As for quenched alloys, the texture is practically isotropic and GS values are low, independent of the alloy composition. In CW materials, the density of ‹c›- dislocations greatly affects the irradiation growth strain. Particles of Zr(Fe,Cr)2 and Zr2(Fe,Ni) phases in Zry-2 as well as Zr(Nb,Fe)2 in NSF and E635 are depleted in iron under irradiation. The Fe goes into the matrix and modifies its properties. The HCP lattice structure in the Laves phases in NSF and E635 changes into BCC (β-Nb-type). FCC (Zr,Nb)2Fe precipitates preserve on the whole their composition and structure; no amorphization of the Nb-containing precipitates is observed. The Zr2(Fe,Ni) precipitates with a BCT lattice remain crystalline, and HCP Zr(Cr,Fe)2 precipitates undergo amorphization. The average particle size in the irradiated alloys is larger and the concentration is a little lower as compared to the unirradiated ones. Irradiation-induced fine dispersed precipitates about 3 nm in size, probably enriched in niobium, appear in NSF and E635. The observed changes of microhardness are discussed from the viewpoint of generation of radiation defects (clusters, dislocation loops), evolution of the initial dislocation structure, and matrix composition (enrichment in Fe, Cr, and, probably, Nb).


    zirconium alloys, irradiation-induced growth, microstructure, microhardness, radiation damages and phase composition

    Author Information:

    Kobylyansky, G. P.
    FSUE SSC RIAR, Russia, Ulyanovsk region, Dimitrovgrad,

    Novoselov, A. E.
    FSUE SSC RIAR, Russia, Ulyanovsk region, Dimitrovgrad,

    Ostrovsky, Z. E.
    FSUE SSC RIAR, Russia, Ulyanovsk region, Dimitrovgrad,

    Obukhov, A. V.
    FSUE SSC RIAR, Russia, Ulyanovsk region, Dimitrovgrad,

    Shishin, V. Yu.
    FSUE SSC RIAR, Russia, Ulyanovsk region, Dimitrovgrad,

    Shishov, V. N.
    FSUE VNIINM, Russia, Moscow,

    Nikulina, A. V.
    FSUE VNIINM, Russia, Moscow,

    Peregud, M. M.
    FSUE VNIINM, Russia, Moscow,

    Mahmood, S. T.
    Global Nuclear Fuel,

    White, D. W.
    Global Nuclear Fuel,

    Lin, Y -P.
    Global Nuclear Fuel,

    Dubecky, M. A.
    Global Nuclear Fuel,

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP48156S