Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application

J Li (Corresponding Author), W Zheng, Sami Penttilä, P Liu, O T Woo, D Guzonas

    Research output: Contribution to journalArticleScientificpeer-review

    22 Citations (Scopus)

    Abstract

    In the past few years, significant progress has been made in materials selection for Gen-IV SCWR fuel cladding applications. Current studies indicate that austenite stainless steels such as 310H are promising candidates for in-core applications. Alloys in this group are promising for their corrosion resistance, SCC resistance, high temperature mechanical properties and creep resistance at temperatures up to 700 °C. However, one under-studied area of this alloy is the long-term microstructure stability under the proposed reactor operating condition. Unstable microstructure not only results in embrittlement but also has the potential to reduce their resistance to corrosion or stress-corrosion cracking. In this study, stainless steels 310H and 304H were tested for their SCWR corrosion resistance and microstructure stability.
    Original languageEnglish
    Pages (from-to)7-11
    Number of pages5
    JournalJournal of Nuclear Materials
    Volume454
    Issue number1-3
    DOIs
    Publication statusPublished - 2014
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Stainless Steel
    stainless steels
    Stainless steel
    corrosion resistance
    microstructure
    Microstructure
    Corrosion resistance
    materials selection
    stress corrosion cracking
    creep strength
    Creep resistance
    embrittlement
    Embrittlement
    Stress corrosion cracking
    austenite
    Austenite
    corrosion
    reactors
    mechanical properties
    Corrosion

    Cite this

    Li, J ; Zheng, W ; Penttilä, Sami ; Liu, P ; Woo, O T ; Guzonas, D. / Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application. In: Journal of Nuclear Materials. 2014 ; Vol. 454, No. 1-3. pp. 7-11.
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    title = "Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application",
    abstract = "In the past few years, significant progress has been made in materials selection for Gen-IV SCWR fuel cladding applications. Current studies indicate that austenite stainless steels such as 310H are promising candidates for in-core applications. Alloys in this group are promising for their corrosion resistance, SCC resistance, high temperature mechanical properties and creep resistance at temperatures up to 700 °C. However, one under-studied area of this alloy is the long-term microstructure stability under the proposed reactor operating condition. Unstable microstructure not only results in embrittlement but also has the potential to reduce their resistance to corrosion or stress-corrosion cracking. In this study, stainless steels 310H and 304H were tested for their SCWR corrosion resistance and microstructure stability.",
    author = "J Li and W Zheng and Sami Penttil{\"a} and P Liu and Woo, {O T} and D Guzonas",
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    Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application. / Li, J (Corresponding Author); Zheng, W; Penttilä, Sami; Liu, P; Woo, O T; Guzonas, D.

    In: Journal of Nuclear Materials, Vol. 454, No. 1-3, 2014, p. 7-11.

    Research output: Contribution to journalArticleScientificpeer-review

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    T1 - Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application

    AU - Li, J

    AU - Zheng, W

    AU - Penttilä, Sami

    AU - Liu, P

    AU - Woo, O T

    AU - Guzonas, D

    PY - 2014

    Y1 - 2014

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    AB - In the past few years, significant progress has been made in materials selection for Gen-IV SCWR fuel cladding applications. Current studies indicate that austenite stainless steels such as 310H are promising candidates for in-core applications. Alloys in this group are promising for their corrosion resistance, SCC resistance, high temperature mechanical properties and creep resistance at temperatures up to 700 °C. However, one under-studied area of this alloy is the long-term microstructure stability under the proposed reactor operating condition. Unstable microstructure not only results in embrittlement but also has the potential to reduce their resistance to corrosion or stress-corrosion cracking. In this study, stainless steels 310H and 304H were tested for their SCWR corrosion resistance and microstructure stability.

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