On flux effects in a low alloy steel from a Swedish reactor pressure vessel

Magnus Boåsen, Pål Efsing, Ulla Ehrnstén

    Research output: Contribution to journalArticleScientificpeer-review

    3 Citations (Scopus)

    Abstract

    This study aims to investigate the presence of Unstable Matrix Defects in irradiated pressure vessel steel from weldments of the Swedish PWR Ringhals 4 (R4). Hardness tests have been performed on low flux (surveillance material) and high flux (Halden reactor) irradiated material samples in combination with heat treatments at temperatures of 330, 360 and 390 °C in order to reveal eventual recovery of any hardening features induced by irradiation. The experiments carried out in this study could not reveal any hardness recovery related to Unstable Matrix Defects at relevant temperatures. However, a difference in hardness recovery was found between the low and the high flux samples at heat treatments at higher temperatures than expected for the annihilation of Unstable Matrix Defects–the observed recovery is here attributed to differences of the solute clusters formed by the high and low flux irradiations.

    Original languageEnglish
    Pages (from-to)110-119
    Number of pages10
    JournalJournal of Nuclear Materials
    Volume484
    DOIs
    Publication statusPublished - 2017
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    pressure vessels
    high strength steels
    Pressure vessels
    High strength steel
    recovery
    reactors
    Fluxes
    Recovery
    Hardness
    Halden Boiling Water Reactor
    heat treatment
    hardness
    matrices
    reactor materials
    Heat treatment
    Irradiation
    hardness tests
    Defects
    irradiation
    defects

    Keywords

    • nuclear
    • pressure vessel steel
    • embrittlement
    • hardness

    Cite this

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    title = "On flux effects in a low alloy steel from a Swedish reactor pressure vessel",
    abstract = "This study aims to investigate the presence of Unstable Matrix Defects in irradiated pressure vessel steel from weldments of the Swedish PWR Ringhals 4 (R4). Hardness tests have been performed on low flux (surveillance material) and high flux (Halden reactor) irradiated material samples in combination with heat treatments at temperatures of 330, 360 and 390 °C in order to reveal eventual recovery of any hardening features induced by irradiation. The experiments carried out in this study could not reveal any hardness recovery related to Unstable Matrix Defects at relevant temperatures. However, a difference in hardness recovery was found between the low and the high flux samples at heat treatments at higher temperatures than expected for the annihilation of Unstable Matrix Defects–the observed recovery is here attributed to differences of the solute clusters formed by the high and low flux irradiations.",
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    author = "Magnus Bo{\aa}sen and P{\aa}l Efsing and Ulla Ehrnst{\'e}n",
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    On flux effects in a low alloy steel from a Swedish reactor pressure vessel. / Boåsen, Magnus; Efsing, Pål; Ehrnstén, Ulla.

    In: Journal of Nuclear Materials, Vol. 484, 2017, p. 110-119.

    Research output: Contribution to journalArticleScientificpeer-review

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    AU - Ehrnstén, Ulla

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