Thermal ageing and short-range ordering of Alloy 690 between 350 and 550 °C

Roman Mouginot, Teemu Sarikka, Mikko Heikkilä, Mykola Ivanchenko, Ulla Ehrnstén, Young Suk Kim, Soo Kimsung, Hannu Hänninen

    Research output: Contribution to journalArticleScientificpeer-review

    10 Citations (Scopus)

    Abstract

    Thermal ageing of Alloy 690 triggers an intergranular (IG) carbide precipitation and is known to promote an ordering reaction causing lattice contraction. It may affect the long-term primary water stress corrosion cracking (PWSCC) resistance of pressurized water reactor (PWR) components. Four conditions of Alloy 690 (solution annealed, cold-rolled and/or heat-treated) were aged between 350 and 550 °C for 10 000 h and characterized. Although no direct observation of ordering was made, variations in hardness and lattice parameter were attributed to the formation of short-range ordering (SRO) in all conditions with a peak level at 420 °C, consistent with the literature. Prior heat treatment induced ordering before thermal ageing. At higher temperatures, stress relaxation, recrystallization and ?-Cr precipitation were observed in the cold-worked samples, while a disordering reaction was inferred in all samples based on a decrease in hardness. IG precipitation of M23C6 carbides increased with increasing ageing temperature in all conditions, as well as diffusion-induced grain boundary migration (DIGM).
    Original languageEnglish
    Pages (from-to)56-66
    Number of pages11
    JournalJournal of Nuclear Materials
    Volume485
    DOIs
    Publication statusPublished - 1 Mar 2017
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Thermal aging
    Carbides
    Hardness
    carbides
    Pressurized water reactors
    Stress relaxation
    hardness
    Stress corrosion cracking
    Lattice constants
    pressurized water reactors
    stress corrosion cracking
    Grain boundaries
    Aging of materials
    Heat treatment
    stress relaxation
    Temperature
    contraction
    Water
    lattice parameters
    heat treatment

    Keywords

    • Alloy 690
    • Thermal ageing
    • Short-range ordering
    • Ni2Cr
    • Carbide precipitation
    • Cold work
    • Strain localization
    • Ni Cr

    Cite this

    Mouginot, R., Sarikka, T., Heikkilä, M., Ivanchenko, M., Ehrnstén, U., Kim, Y. S., ... Hänninen, H. (2017). Thermal ageing and short-range ordering of Alloy 690 between 350 and 550 °C. Journal of Nuclear Materials, 485, 56-66. https://doi.org/10.1016/j.jnucmat.2016.12.031
    Mouginot, Roman ; Sarikka, Teemu ; Heikkilä, Mikko ; Ivanchenko, Mykola ; Ehrnstén, Ulla ; Kim, Young Suk ; Kimsung, Soo ; Hänninen, Hannu. / Thermal ageing and short-range ordering of Alloy 690 between 350 and 550 °C. In: Journal of Nuclear Materials. 2017 ; Vol. 485. pp. 56-66.
    @article{fd37bb3dee014f64b5bf687c9c57edf6,
    title = "Thermal ageing and short-range ordering of Alloy 690 between 350 and 550 °C",
    abstract = "Thermal ageing of Alloy 690 triggers an intergranular (IG) carbide precipitation and is known to promote an ordering reaction causing lattice contraction. It may affect the long-term primary water stress corrosion cracking (PWSCC) resistance of pressurized water reactor (PWR) components. Four conditions of Alloy 690 (solution annealed, cold-rolled and/or heat-treated) were aged between 350 and 550 °C for 10 000 h and characterized. Although no direct observation of ordering was made, variations in hardness and lattice parameter were attributed to the formation of short-range ordering (SRO) in all conditions with a peak level at 420 °C, consistent with the literature. Prior heat treatment induced ordering before thermal ageing. At higher temperatures, stress relaxation, recrystallization and ?-Cr precipitation were observed in the cold-worked samples, while a disordering reaction was inferred in all samples based on a decrease in hardness. IG precipitation of M23C6 carbides increased with increasing ageing temperature in all conditions, as well as diffusion-induced grain boundary migration (DIGM).",
    keywords = "Alloy 690, Thermal ageing, Short-range ordering, Ni2Cr, Carbide precipitation, Cold work, Strain localization, Ni Cr",
    author = "Roman Mouginot and Teemu Sarikka and Mikko Heikkil{\"a} and Mykola Ivanchenko and Ulla Ehrnst{\'e}n and Kim, {Young Suk} and Soo Kimsung and Hannu H{\"a}nninen",
    year = "2017",
    month = "3",
    day = "1",
    doi = "10.1016/j.jnucmat.2016.12.031",
    language = "English",
    volume = "485",
    pages = "56--66",
    journal = "Journal of Nuclear Materials",
    issn = "0022-3115",
    publisher = "Elsevier",

    }

    Mouginot, R, Sarikka, T, Heikkilä, M, Ivanchenko, M, Ehrnstén, U, Kim, YS, Kimsung, S & Hänninen, H 2017, 'Thermal ageing and short-range ordering of Alloy 690 between 350 and 550 °C', Journal of Nuclear Materials, vol. 485, pp. 56-66. https://doi.org/10.1016/j.jnucmat.2016.12.031

    Thermal ageing and short-range ordering of Alloy 690 between 350 and 550 °C. / Mouginot, Roman; Sarikka, Teemu; Heikkilä, Mikko; Ivanchenko, Mykola; Ehrnstén, Ulla; Kim, Young Suk; Kimsung, Soo; Hänninen, Hannu.

    In: Journal of Nuclear Materials, Vol. 485, 01.03.2017, p. 56-66.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Thermal ageing and short-range ordering of Alloy 690 between 350 and 550 °C

    AU - Mouginot, Roman

    AU - Sarikka, Teemu

    AU - Heikkilä, Mikko

    AU - Ivanchenko, Mykola

    AU - Ehrnstén, Ulla

    AU - Kim, Young Suk

    AU - Kimsung, Soo

    AU - Hänninen, Hannu

    PY - 2017/3/1

    Y1 - 2017/3/1

    N2 - Thermal ageing of Alloy 690 triggers an intergranular (IG) carbide precipitation and is known to promote an ordering reaction causing lattice contraction. It may affect the long-term primary water stress corrosion cracking (PWSCC) resistance of pressurized water reactor (PWR) components. Four conditions of Alloy 690 (solution annealed, cold-rolled and/or heat-treated) were aged between 350 and 550 °C for 10 000 h and characterized. Although no direct observation of ordering was made, variations in hardness and lattice parameter were attributed to the formation of short-range ordering (SRO) in all conditions with a peak level at 420 °C, consistent with the literature. Prior heat treatment induced ordering before thermal ageing. At higher temperatures, stress relaxation, recrystallization and ?-Cr precipitation were observed in the cold-worked samples, while a disordering reaction was inferred in all samples based on a decrease in hardness. IG precipitation of M23C6 carbides increased with increasing ageing temperature in all conditions, as well as diffusion-induced grain boundary migration (DIGM).

    AB - Thermal ageing of Alloy 690 triggers an intergranular (IG) carbide precipitation and is known to promote an ordering reaction causing lattice contraction. It may affect the long-term primary water stress corrosion cracking (PWSCC) resistance of pressurized water reactor (PWR) components. Four conditions of Alloy 690 (solution annealed, cold-rolled and/or heat-treated) were aged between 350 and 550 °C for 10 000 h and characterized. Although no direct observation of ordering was made, variations in hardness and lattice parameter were attributed to the formation of short-range ordering (SRO) in all conditions with a peak level at 420 °C, consistent with the literature. Prior heat treatment induced ordering before thermal ageing. At higher temperatures, stress relaxation, recrystallization and ?-Cr precipitation were observed in the cold-worked samples, while a disordering reaction was inferred in all samples based on a decrease in hardness. IG precipitation of M23C6 carbides increased with increasing ageing temperature in all conditions, as well as diffusion-induced grain boundary migration (DIGM).

    KW - Alloy 690

    KW - Thermal ageing

    KW - Short-range ordering

    KW - Ni2Cr

    KW - Carbide precipitation

    KW - Cold work

    KW - Strain localization

    KW - Ni Cr

    UR - http://www.scopus.com/inward/record.url?scp=85007460171&partnerID=8YFLogxK

    U2 - 10.1016/j.jnucmat.2016.12.031

    DO - 10.1016/j.jnucmat.2016.12.031

    M3 - Article

    VL - 485

    SP - 56

    EP - 66

    JO - Journal of Nuclear Materials

    JF - Journal of Nuclear Materials

    SN - 0022-3115

    ER -