Volume 5, Issue 4 (April 2008)

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

    (Received 19 March 2007; accepted 22 March 2008)

    Published Online: 2008

    CODEN: JAIOAD

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    Abstract

    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>1 MeV), 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).


    Author Information:

    Kobylyansky, G. P.
    FSUE SSC RIAR, Dimitrovgrad,

    Novoselov, A. E.
    FSUE SSC RIAR, Dimitrovgrad,

    Ostrovsky, Z. E.
    FSUE SSC RIAR, Dimitrovgrad,

    Obukhov, A. V.
    FSUE SSC RIAR, Dimitrovgrad,

    Shishin, V. Yu.
    FSUE SSC RIAR, Dimitrovgrad,

    Shishov, V. N.
    FSUE VNIINM, Moscow,

    Nikulina, A. V.
    FSUE VNIINM, Moscow,

    Peregud, M. M.
    FSUE VNIINM, Moscow,

    Mahmood, S. T.
    Global Nuclear Fuel, USA

    White, D. W.
    Global Nuclear Fuel, USA

    Lin, Y-P.
    Global Nuclear Fuel, USA

    Dubecky, M. A.
    Global Nuclear Fuel, USA


    Stock #: JAI101115

    ISSN: 1546-962X

    DOI: 10.1520/JAI101115

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    Author
    Title Irradiation-Induced Growth and Microstructure of Recrystallized, Cold Worked and Quenched Zircaloy-2, NSF, and E635 Alloys
    Symposium 15th International Symposium on Zirconium in the Nuclear Industry, 2007-06-28
    Committee B10