Corrosion behaviour of bare and NiCrAlY coated alloy 214 in SCW at 700C

Suzan Bsat (Corresponding Author), Xiao Huang, Sami Penttilä

    Research output: Contribution to journalArticleScientificpeer-review

    3 Citations (Scopus)

    Abstract

    Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have resulted in renewed interest in nuclear energy as an essential part of the energy mix for the future. Many countries worldwide including Canada, China, and EU are currently undertaking the design of generation IV supercritical water-cooled reactor (SCWR) with higher thermodynamic efficiency and considerable plant simplification. The identification of appropriate materials for in-core and out-of-core components to contain the supercritical water (SCW) coolant is one of the major challenges for the design of SCWR. This study is carried out to evaluate the oxidation/corrosion behaviors of bare alloy 214 and NiCrAlY coated 214 under SCW at a temperature of 700 C/25 MPa for 1000 h. The results show that chromium and nickel based oxide forms on the bare surface after exposure in SCW for 1000 h. A dense and adhered oxide layer, consisting of Cr 2O 3 with spinel (Ni(Cr, Al) 2O 4), was observed on NiCrAlY surface after 1000 h in SCW.

    Original languageEnglish
    Article number011017
    Pages (from-to)377-389
    JournalJournal of Nuclear Engineering and Radiation Science
    Volume4
    Issue number1
    DOIs
    Publication statusPublished - 2017
    MoE publication typeA1 Journal article-refereed
    Event8th International Symposium on Super-Critical Water-cooled Reactors, ISSCWR-8 - Chengdu, China
    Duration: 13 Mar 201715 Mar 2017

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    corrosion
    water cooled reactors
    Water cooled reactors
    Corrosion
    water
    Water
    thermodynamic efficiency
    fossil fuels
    Oxides
    oxides
    greenhouses
    coolants
    nuclear energy
    simplification
    Gas emissions
    Canada
    Fossil fuels
    Greenhouse gases
    Nuclear energy
    Coolants

    Cite this

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    title = "Corrosion behaviour of bare and NiCrAlY coated alloy 214 in SCW at 700C",
    abstract = "Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have resulted in renewed interest in nuclear energy as an essential part of the energy mix for the future. Many countries worldwide including Canada, China, and EU are currently undertaking the design of generation IV supercritical water-cooled reactor (SCWR) with higher thermodynamic efficiency and considerable plant simplification. The identification of appropriate materials for in-core and out-of-core components to contain the supercritical water (SCW) coolant is one of the major challenges for the design of SCWR. This study is carried out to evaluate the oxidation/corrosion behaviors of bare alloy 214 and NiCrAlY coated 214 under SCW at a temperature of 700 C/25 MPa for 1000 h. The results show that chromium and nickel based oxide forms on the bare surface after exposure in SCW for 1000 h. A dense and adhered oxide layer, consisting of Cr 2O 3 with spinel (Ni(Cr, Al) 2O 4), was observed on NiCrAlY surface after 1000 h in SCW.",
    author = "Suzan Bsat and Xiao Huang and Sami Penttil{\"a}",
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    Corrosion behaviour of bare and NiCrAlY coated alloy 214 in SCW at 700C. / Bsat, Suzan (Corresponding Author); Huang, Xiao; Penttilä, Sami.

    In: Journal of Nuclear Engineering and Radiation Science, Vol. 4, No. 1, 011017, 2017, p. 377-389.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Corrosion behaviour of bare and NiCrAlY coated alloy 214 in SCW at 700C

    AU - Bsat, Suzan

    AU - Huang, Xiao

    AU - Penttilä, Sami

    PY - 2017

    Y1 - 2017

    N2 - Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have resulted in renewed interest in nuclear energy as an essential part of the energy mix for the future. Many countries worldwide including Canada, China, and EU are currently undertaking the design of generation IV supercritical water-cooled reactor (SCWR) with higher thermodynamic efficiency and considerable plant simplification. The identification of appropriate materials for in-core and out-of-core components to contain the supercritical water (SCW) coolant is one of the major challenges for the design of SCWR. This study is carried out to evaluate the oxidation/corrosion behaviors of bare alloy 214 and NiCrAlY coated 214 under SCW at a temperature of 700 C/25 MPa for 1000 h. The results show that chromium and nickel based oxide forms on the bare surface after exposure in SCW for 1000 h. A dense and adhered oxide layer, consisting of Cr 2O 3 with spinel (Ni(Cr, Al) 2O 4), was observed on NiCrAlY surface after 1000 h in SCW.

    AB - Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have resulted in renewed interest in nuclear energy as an essential part of the energy mix for the future. Many countries worldwide including Canada, China, and EU are currently undertaking the design of generation IV supercritical water-cooled reactor (SCWR) with higher thermodynamic efficiency and considerable plant simplification. The identification of appropriate materials for in-core and out-of-core components to contain the supercritical water (SCW) coolant is one of the major challenges for the design of SCWR. This study is carried out to evaluate the oxidation/corrosion behaviors of bare alloy 214 and NiCrAlY coated 214 under SCW at a temperature of 700 C/25 MPa for 1000 h. The results show that chromium and nickel based oxide forms on the bare surface after exposure in SCW for 1000 h. A dense and adhered oxide layer, consisting of Cr 2O 3 with spinel (Ni(Cr, Al) 2O 4), was observed on NiCrAlY surface after 1000 h in SCW.

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