Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor

Ken R. Anderson (Corresponding Author), Wade Karlsen, Mykola Ivanchenko, Jesse J. Carter, Richard W. Smith

    Research output: Contribution to journalArticleResearchpeer-review

    Abstract

    Post-irradiation examination (PIE) in the form of transmission electron microscopy (TEM) was used to characterize the microstructure of several specimens of Zircaloy-2 and Zircaloy-2 plus 1% Nb that had previously underwent in-pile creep testing in the HALDEN reactor. The purpose of the examination was to explore a microstructural basis for an apparent substantially increased rate of hardening over that observed with similar materials in the higher fast-flux environments of the ATR or HFIR, and to investigate the increased creep strength exhibited by the Nb-containing alloy relative to pure Zircaloy-2. The analysis of irradiation-induced defects indicated a higher than expected density, which was consistent with the observed high hardening rate. Modeling based on mean field rate theory suggests the lower neutron flux in the HALDEN reactor results in a higher fraction of irradiation-induced defects being available for sink (loop) nucleation and growth.

    LanguageEnglish
    Pages260-270
    Number of pages11
    JournalJournal of Nuclear Materials
    Volume513
    DOIs
    Publication statusPublished - Jan 2019
    MoE publication typeNot Eligible

    Fingerprint

    Zircaloy 2 (trademark)
    Creep testing
    zirconium alloys
    Zirconium alloys
    piles
    Piles
    examination
    reactors
    Irradiation
    hardening
    irradiation
    Hardening
    high flux isotope reactors
    creep strength
    Defects
    Neutron flux
    defects
    flux (rate)
    sinks
    Creep

    Keywords

    • In-pile creep
    • Microstructure
    • Neutron-irradiated
    • Rate-theory
    • Zircaloy-2

    OKM Publication Types

    • A1 Refereed journal article

    OKM Open Access Status

    • 0 Not Open Access

    ASJC Scopus subject areas

    • Nuclear and High Energy Physics
    • Nuclear Energy and Engineering
    • Materials Science(all)

    Cite this

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    title = "Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor",
    abstract = "Post-irradiation examination (PIE) in the form of transmission electron microscopy (TEM) was used to characterize the microstructure of several specimens of Zircaloy-2 and Zircaloy-2 plus 1{\%} Nb that had previously underwent in-pile creep testing in the HALDEN reactor. The purpose of the examination was to explore a microstructural basis for an apparent substantially increased rate of hardening over that observed with similar materials in the higher fast-flux environments of the ATR or HFIR, and to investigate the increased creep strength exhibited by the Nb-containing alloy relative to pure Zircaloy-2. The analysis of irradiation-induced defects indicated a higher than expected density, which was consistent with the observed high hardening rate. Modeling based on mean field rate theory suggests the lower neutron flux in the HALDEN reactor results in a higher fraction of irradiation-induced defects being available for sink (loop) nucleation and growth.",
    keywords = "In-pile creep, Microstructure, Neutron-irradiated, Rate-theory, Zircaloy-2",
    author = "Anderson, {Ken R.} and Wade Karlsen and Mykola Ivanchenko and Carter, {Jesse J.} and Smith, {Richard W.}",
    year = "2019",
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    language = "English",
    volume = "513",
    pages = "260--270",
    journal = "Journal of Nuclear Materials",
    issn = "0022-3115",
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    Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor. / Anderson, Ken R. (Corresponding Author); Karlsen, Wade; Ivanchenko, Mykola; Carter, Jesse J.; Smith, Richard W.

    In: Journal of Nuclear Materials, Vol. 513, 01.2019, p. 260-270.

    Research output: Contribution to journalArticleResearchpeer-review

    TY - JOUR

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    AU - Anderson, Ken R.

    AU - Karlsen, Wade

    AU - Ivanchenko, Mykola

    AU - Carter, Jesse J.

    AU - Smith, Richard W.

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    AB - Post-irradiation examination (PIE) in the form of transmission electron microscopy (TEM) was used to characterize the microstructure of several specimens of Zircaloy-2 and Zircaloy-2 plus 1% Nb that had previously underwent in-pile creep testing in the HALDEN reactor. The purpose of the examination was to explore a microstructural basis for an apparent substantially increased rate of hardening over that observed with similar materials in the higher fast-flux environments of the ATR or HFIR, and to investigate the increased creep strength exhibited by the Nb-containing alloy relative to pure Zircaloy-2. The analysis of irradiation-induced defects indicated a higher than expected density, which was consistent with the observed high hardening rate. Modeling based on mean field rate theory suggests the lower neutron flux in the HALDEN reactor results in a higher fraction of irradiation-induced defects being available for sink (loop) nucleation and growth.

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