Effect of heat treatments on precipitate microstructure and mechanical properties of a CuCrZr alloy

D. J. Edwards (Corresponding Author), B. N. Singh, Seppo Tähtinen

    Research output: Contribution to journalArticleScientificpeer-review

    47 Citations (Scopus)

    Abstract

    The precipitate microstructure of prime aged CuCrZr was coarsened by overaging to see if the larger precipitates could prevent the initiation of plastic flow localization in irradiated CuCrZr. A number of tensile and fracture toughness specimens of prime aged CuCrZr alloy were given overaging treatments at 873 K for 1, 2 and 4 h. A subset of these specimens were irradiated with fission neutrons in the BR-2 reactor at Mol (Belgium) at 333 K and 573 K to a dose level of ¡­0.3 dpa. Both unirradiated and irradiated tensile specimens were tested at 295 K, 333 K and 573 K. Fracture toughness tests were carried out at 293, 333 and 573 K. Transmission electron microscopy was used to investigate the effects of overaging, subsequent irradiation and the effect of deformation. The results indicate that the overaging treatment of 873 K for 1 h produced a precipitate microstructure that improved the plastic instability, overall ductility and fracture toughness.
    Original languageEnglish
    Pages (from-to)904-909
    JournalJournal of Nuclear Materials
    Volume367-370
    Issue numberPart. B
    DOIs
    Publication statusPublished - 2007
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    fracture strength
    Fracture toughness
    Precipitates
    precipitates
    heat treatment
    Heat treatment
    mechanical properties
    toughness
    Mechanical properties
    microstructure
    Microstructure
    Belgium
    plastic flow
    ductility
    Plastic flow
    set theory
    fission
    Ductility
    Neutrons
    plastics

    Keywords

    • CuCrZr alloy
    • copper
    • chromium
    • zirconium
    • zirconium alloys
    • heat treatment

    Cite this

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    abstract = "The precipitate microstructure of prime aged CuCrZr was coarsened by overaging to see if the larger precipitates could prevent the initiation of plastic flow localization in irradiated CuCrZr. A number of tensile and fracture toughness specimens of prime aged CuCrZr alloy were given overaging treatments at 873 K for 1, 2 and 4 h. A subset of these specimens were irradiated with fission neutrons in the BR-2 reactor at Mol (Belgium) at 333 K and 573 K to a dose level of ¡­0.3 dpa. Both unirradiated and irradiated tensile specimens were tested at 295 K, 333 K and 573 K. Fracture toughness tests were carried out at 293, 333 and 573 K. Transmission electron microscopy was used to investigate the effects of overaging, subsequent irradiation and the effect of deformation. The results indicate that the overaging treatment of 873 K for 1 h produced a precipitate microstructure that improved the plastic instability, overall ductility and fracture toughness.",
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    author = "Edwards, {D. J.} and Singh, {B. N.} and Seppo T{\"a}htinen",
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    Effect of heat treatments on precipitate microstructure and mechanical properties of a CuCrZr alloy. / Edwards, D. J. (Corresponding Author); Singh, B. N.; Tähtinen, Seppo.

    In: Journal of Nuclear Materials, Vol. 367-370 , No. Part. B, 2007, p. 904-909.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Effect of heat treatments on precipitate microstructure and mechanical properties of a CuCrZr alloy

    AU - Edwards, D. J.

    AU - Singh, B. N.

    AU - Tähtinen, Seppo

    PY - 2007

    Y1 - 2007

    N2 - The precipitate microstructure of prime aged CuCrZr was coarsened by overaging to see if the larger precipitates could prevent the initiation of plastic flow localization in irradiated CuCrZr. A number of tensile and fracture toughness specimens of prime aged CuCrZr alloy were given overaging treatments at 873 K for 1, 2 and 4 h. A subset of these specimens were irradiated with fission neutrons in the BR-2 reactor at Mol (Belgium) at 333 K and 573 K to a dose level of ¡­0.3 dpa. Both unirradiated and irradiated tensile specimens were tested at 295 K, 333 K and 573 K. Fracture toughness tests were carried out at 293, 333 and 573 K. Transmission electron microscopy was used to investigate the effects of overaging, subsequent irradiation and the effect of deformation. The results indicate that the overaging treatment of 873 K for 1 h produced a precipitate microstructure that improved the plastic instability, overall ductility and fracture toughness.

    AB - The precipitate microstructure of prime aged CuCrZr was coarsened by overaging to see if the larger precipitates could prevent the initiation of plastic flow localization in irradiated CuCrZr. A number of tensile and fracture toughness specimens of prime aged CuCrZr alloy were given overaging treatments at 873 K for 1, 2 and 4 h. A subset of these specimens were irradiated with fission neutrons in the BR-2 reactor at Mol (Belgium) at 333 K and 573 K to a dose level of ¡­0.3 dpa. Both unirradiated and irradiated tensile specimens were tested at 295 K, 333 K and 573 K. Fracture toughness tests were carried out at 293, 333 and 573 K. Transmission electron microscopy was used to investigate the effects of overaging, subsequent irradiation and the effect of deformation. The results indicate that the overaging treatment of 873 K for 1 h produced a precipitate microstructure that improved the plastic instability, overall ductility and fracture toughness.

    KW - CuCrZr alloy

    KW - copper

    KW - chromium

    KW - zirconium

    KW - zirconium alloys

    KW - heat treatment

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    DO - 10.1016/j.jnucmat.2007.03.064

    M3 - Article

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    JO - Journal of Nuclear Materials

    JF - Journal of Nuclear Materials

    SN - 0022-3115

    IS - Part. B

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