Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging

Teemu Sarikka, Roman Mouginot, Matias Ahonen, Sebastian Lindqvist, Ulla Ehrnstén, Pekka Nevasmaa, Hannu Hänninen

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Abstract

    The safe-end dissimilar metal weld (DMW) joining the reactor pressure vessel to the main coolant piping is one of the most critical DMWs in a nuclear power plant (NPP). DMWs have varying microstructures at a short distance across the ferritic-austenitic fusion boundary (FB) region. This microstructural variation affects the mechanical properties and fracture behavior and may evolve as a result of thermal aging during long-term operation of an NPP. This paper presents microstructural characterization performed for as-manufactured and 5000 h and 10,000 h thermally aged narrow-gap DMW representing a safe-end DMW of a modern pressurized water reactor (PWR) NPP. The most significant result of the study is that the thermal aging leads to a significant decrease in a hardness gradient observed across the ferritic-austenitic FB of the as-manufactured DMW.

    Original languageEnglish
    Title of host publicationProceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
    EditorsJohn H. Jackson, Denise Paraventi, Michael Wright
    PublisherSpringer
    Pages763-777
    Number of pages15
    Volume2
    ISBN (Electronic)978-3-319-68454-3
    ISBN (Print)978-3-319-68453-6
    DOIs
    Publication statusPublished - 1 Jan 2018
    MoE publication typeA4 Article in a conference publication
    Event18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States
    Duration: 13 Aug 201717 Aug 2017

    Publication series

    SeriesMinerals, Metals and Materials Series
    NumberPart F11
    ISSN2367-1181

    Conference

    Conference18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
    Abbreviated titleEDM 2017
    CountryUnited States
    CityPortland
    Period13/08/1717/08/17

    Fingerprint

    Dissimilar metals
    Welds
    Aging of materials
    Nuclear power plants
    Thermal aging
    Fusion reactions
    Pressurized water reactors
    Pressure vessels
    Joining
    Coolants
    Hardness
    Mechanical properties
    Microstructure

    Keywords

    • Aging
    • Dissimilar metal weld
    • Microstructural characterization
    • Ni-base alloy

    Cite this

    Sarikka, T., Mouginot, R., Ahonen, M., Lindqvist, S., Ehrnstén, U., Nevasmaa, P., & Hänninen, H. (2018). Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging. In J. H. Jackson, D. Paraventi, & M. Wright (Eds.), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (Vol. 2, pp. 763-777). Springer. Minerals, Metals and Materials Series, No. Part F11 https://doi.org/10.1007/978-3-319-68454-3_58
    Sarikka, Teemu ; Mouginot, Roman ; Ahonen, Matias ; Lindqvist, Sebastian ; Ehrnstén, Ulla ; Nevasmaa, Pekka ; Hänninen, Hannu. / Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. editor / John H. Jackson ; Denise Paraventi ; Michael Wright. Vol. 2 Springer, 2018. pp. 763-777 (Minerals, Metals and Materials Series; No. Part F11).
    @inproceedings{59b74c0e810147f29e498e963199af12,
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    abstract = "The safe-end dissimilar metal weld (DMW) joining the reactor pressure vessel to the main coolant piping is one of the most critical DMWs in a nuclear power plant (NPP). DMWs have varying microstructures at a short distance across the ferritic-austenitic fusion boundary (FB) region. This microstructural variation affects the mechanical properties and fracture behavior and may evolve as a result of thermal aging during long-term operation of an NPP. This paper presents microstructural characterization performed for as-manufactured and 5000 h and 10,000 h thermally aged narrow-gap DMW representing a safe-end DMW of a modern pressurized water reactor (PWR) NPP. The most significant result of the study is that the thermal aging leads to a significant decrease in a hardness gradient observed across the ferritic-austenitic FB of the as-manufactured DMW.",
    keywords = "Aging, Dissimilar metal weld, Microstructural characterization, Ni-base alloy",
    author = "Teemu Sarikka and Roman Mouginot and Matias Ahonen and Sebastian Lindqvist and Ulla Ehrnst{\'e}n and Pekka Nevasmaa and Hannu H{\"a}nninen",
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    Sarikka, T, Mouginot, R, Ahonen, M, Lindqvist, S, Ehrnstén, U, Nevasmaa, P & Hänninen, H 2018, Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging. in JH Jackson, D Paraventi & M Wright (eds), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. vol. 2, Springer, Minerals, Metals and Materials Series, no. Part F11, pp. 763-777, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017, Portland, United States, 13/08/17. https://doi.org/10.1007/978-3-319-68454-3_58

    Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging. / Sarikka, Teemu; Mouginot, Roman; Ahonen, Matias; Lindqvist, Sebastian; Ehrnstén, Ulla; Nevasmaa, Pekka; Hänninen, Hannu.

    Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. ed. / John H. Jackson; Denise Paraventi; Michael Wright. Vol. 2 Springer, 2018. p. 763-777 (Minerals, Metals and Materials Series; No. Part F11).

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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    AU - Ahonen, Matias

    AU - Lindqvist, Sebastian

    AU - Ehrnstén, Ulla

    AU - Nevasmaa, Pekka

    AU - Hänninen, Hannu

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    N2 - The safe-end dissimilar metal weld (DMW) joining the reactor pressure vessel to the main coolant piping is one of the most critical DMWs in a nuclear power plant (NPP). DMWs have varying microstructures at a short distance across the ferritic-austenitic fusion boundary (FB) region. This microstructural variation affects the mechanical properties and fracture behavior and may evolve as a result of thermal aging during long-term operation of an NPP. This paper presents microstructural characterization performed for as-manufactured and 5000 h and 10,000 h thermally aged narrow-gap DMW representing a safe-end DMW of a modern pressurized water reactor (PWR) NPP. The most significant result of the study is that the thermal aging leads to a significant decrease in a hardness gradient observed across the ferritic-austenitic FB of the as-manufactured DMW.

    AB - The safe-end dissimilar metal weld (DMW) joining the reactor pressure vessel to the main coolant piping is one of the most critical DMWs in a nuclear power plant (NPP). DMWs have varying microstructures at a short distance across the ferritic-austenitic fusion boundary (FB) region. This microstructural variation affects the mechanical properties and fracture behavior and may evolve as a result of thermal aging during long-term operation of an NPP. This paper presents microstructural characterization performed for as-manufactured and 5000 h and 10,000 h thermally aged narrow-gap DMW representing a safe-end DMW of a modern pressurized water reactor (PWR) NPP. The most significant result of the study is that the thermal aging leads to a significant decrease in a hardness gradient observed across the ferritic-austenitic FB of the as-manufactured DMW.

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    Sarikka T, Mouginot R, Ahonen M, Lindqvist S, Ehrnstén U, Nevasmaa P et al. Microstructural characterization of alloy 52 narrow-gap dissimilar metal weld after aging. In Jackson JH, Paraventi D, Wright M, editors, Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Vol. 2. Springer. 2018. p. 763-777. (Minerals, Metals and Materials Series; No. Part F11). https://doi.org/10.1007/978-3-319-68454-3_58