Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water

Susan Bsat, Bingjie Xiao, Xiao Huang, Sami Penttilä

    Research output: Contribution to journalArticleScientificpeer-review

    7 Citations (Scopus)

    Abstract

    The choice of materials is of great concern in the construction of Gen IV supercritical water-cooled reactors (SCWRs), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. Material's performance under simulated conditions must be evaluated to support proper material selection by designers. In this study, alloys 800H, 3003 and 304 were tested in SCW at 700 °C and 25 MPa for 1000 h. The results showed that only alloy 3033 experienced weight gain while weight loss was found for alloys 304 and 800H. Based on SEM/EDS and XRD analyses, spinel and Cr2O3, in addition to small amount of Fe2O3, formed on 800H surface, while predominant Cr2O3 and some spinel were present on alloy 3033. Alloy 304 showed no evidence of Cr2O3 on the surface, although some Cr-containing spinel and Fe2O3 were detected on the surface.
    Original languageEnglish
    Pages (from-to)151-163
    Number of pages13
    JournalOxidation of Metals
    Volume89
    Issue number1-2
    Early online date2017
    DOIs
    Publication statusPublished - 2018
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Oxidation
    Water
    Temperature
    Water cooled reactors
    Energy dispersive spectroscopy
    Scanning electron microscopy
    spinell

    Keywords

    • oxidation
    • alloy 800H
    • alloy 3033
    • alloy 304
    • supercritical water-cooled reactor (SCWR)
    • weight change
    • surface oxide
    • SEM
    • XRD

    Cite this

    Bsat, Susan ; Xiao, Bingjie ; Huang, Xiao ; Penttilä, Sami. / Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water. In: Oxidation of Metals. 2018 ; Vol. 89, No. 1-2. pp. 151-163.
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    title = "Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water",
    abstract = "The choice of materials is of great concern in the construction of Gen IV supercritical water-cooled reactors (SCWRs), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. Material's performance under simulated conditions must be evaluated to support proper material selection by designers. In this study, alloys 800H, 3003 and 304 were tested in SCW at 700 °C and 25 MPa for 1000 h. The results showed that only alloy 3033 experienced weight gain while weight loss was found for alloys 304 and 800H. Based on SEM/EDS and XRD analyses, spinel and Cr2O3, in addition to small amount of Fe2O3, formed on 800H surface, while predominant Cr2O3 and some spinel were present on alloy 3033. Alloy 304 showed no evidence of Cr2O3 on the surface, although some Cr-containing spinel and Fe2O3 were detected on the surface.",
    keywords = "oxidation, alloy 800H, alloy 3033, alloy 304, supercritical water-cooled reactor (SCWR), weight change, surface oxide, SEM, XRD",
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    Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water. / Bsat, Susan; Xiao, Bingjie; Huang, Xiao; Penttilä, Sami.

    In: Oxidation of Metals, Vol. 89, No. 1-2, 2018, p. 151-163.

    Research output: Contribution to journalArticleScientificpeer-review

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    T1 - Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water

    AU - Bsat, Susan

    AU - Xiao, Bingjie

    AU - Huang, Xiao

    AU - Penttilä, Sami

    PY - 2018

    Y1 - 2018

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    AB - The choice of materials is of great concern in the construction of Gen IV supercritical water-cooled reactors (SCWRs), particularly the fuel cladding, due to the harsh environment of elevated temperatures and pressures. Material's performance under simulated conditions must be evaluated to support proper material selection by designers. In this study, alloys 800H, 3003 and 304 were tested in SCW at 700 °C and 25 MPa for 1000 h. The results showed that only alloy 3033 experienced weight gain while weight loss was found for alloys 304 and 800H. Based on SEM/EDS and XRD analyses, spinel and Cr2O3, in addition to small amount of Fe2O3, formed on 800H surface, while predominant Cr2O3 and some spinel were present on alloy 3033. Alloy 304 showed no evidence of Cr2O3 on the surface, although some Cr-containing spinel and Fe2O3 were detected on the surface.

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    KW - alloy 3033

    KW - alloy 304

    KW - supercritical water-cooled reactor (SCWR)

    KW - weight change

    KW - surface oxide

    KW - SEM

    KW - XRD

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