Generation IV material issues: Case SCWR

Sami Penttilä, Aki Toivonen, Laura Rissanen, Liisa Heikinheimo

    Research output: Contribution to journalArticleScientificpeer-review

    Abstract

    Six Generation IV nuclear power concepts becoming global research topics accepted by the GenIV international forum (GIF) with common objectives of promoting technological efficiency and safety provide attractive features and demanding new challenges e.g., increased operating temperatures, higher irradiation doses, more aggressive coolants, and/or longer life expectations than GenII and GenIII plants. This paper reviews the performance of commercial candidate materials for in-core super-critical water reactor (SCWR) applications focusing on corrosion, stress corrosion cracking (SCC), and creep issues based on work within the Euratom phase 2 high performance light water reactor phase 2 (HPLWR) project. General corrosion, i.e., oxidation rate tests, and SCC tests have been done on selected iron- and nickel-based alloys at 500°C and 650°C in supercritical water (SCW) at a pressure of 25 MPa with an oxygen concentration of 125-150 ppb in all tests. Constant load creep tests have been done on selected austenitic stainless steel at 650°C in SCW at 25 MPa and 1 ppm O2 and in inert atmospheres of He and 0.1 MPa. Based on materials studies done during the HPLWR Phase2 project, current candidates for European SCWR core internals are austenitic stainless steels having sufficient oxidation and creep resistance up to 500°C or 550°C. High chromium austenitic steels and ferritic/martensitic ODS steels are considered, in longterm, for fuel rod cladding thanks to their good oxidation resistances up to 650°C.
    Original languageEnglish
    Pages (from-to)469-478
    Number of pages10
    JournalJournal of Disaster Research
    Volume5
    Issue number4
    DOIs
    Publication statusPublished - 2010
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Light water reactors
    Oxidation resistance
    Stress corrosion cracking
    Austenitic stainless steel
    Water
    Creep
    Corrosion
    Martensitic steel
    Creep resistance
    Reactor cores
    Austenitic steel
    Ferritic steel
    Nuclear energy
    Coolants
    Dosimetry
    Chromium
    Nickel
    Irradiation
    Iron
    Oxidation

    Keywords

    • GenIV
    • supercritical water
    • corrosion
    • stress corrosion cracking
    • creep
    • austenitic alloy
    • ODS steel

    Cite this

    Penttilä, Sami ; Toivonen, Aki ; Rissanen, Laura ; Heikinheimo, Liisa. / Generation IV material issues : Case SCWR. In: Journal of Disaster Research. 2010 ; Vol. 5, No. 4. pp. 469-478.
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    title = "Generation IV material issues: Case SCWR",
    abstract = "Six Generation IV nuclear power concepts becoming global research topics accepted by the GenIV international forum (GIF) with common objectives of promoting technological efficiency and safety provide attractive features and demanding new challenges e.g., increased operating temperatures, higher irradiation doses, more aggressive coolants, and/or longer life expectations than GenII and GenIII plants. This paper reviews the performance of commercial candidate materials for in-core super-critical water reactor (SCWR) applications focusing on corrosion, stress corrosion cracking (SCC), and creep issues based on work within the Euratom phase 2 high performance light water reactor phase 2 (HPLWR) project. General corrosion, i.e., oxidation rate tests, and SCC tests have been done on selected iron- and nickel-based alloys at 500°C and 650°C in supercritical water (SCW) at a pressure of 25 MPa with an oxygen concentration of 125-150 ppb in all tests. Constant load creep tests have been done on selected austenitic stainless steel at 650°C in SCW at 25 MPa and 1 ppm O2 and in inert atmospheres of He and 0.1 MPa. Based on materials studies done during the HPLWR Phase2 project, current candidates for European SCWR core internals are austenitic stainless steels having sufficient oxidation and creep resistance up to 500°C or 550°C. High chromium austenitic steels and ferritic/martensitic ODS steels are considered, in longterm, for fuel rod cladding thanks to their good oxidation resistances up to 650°C.",
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    author = "Sami Penttil{\"a} and Aki Toivonen and Laura Rissanen and Liisa Heikinheimo",
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    Generation IV material issues : Case SCWR. / Penttilä, Sami; Toivonen, Aki; Rissanen, Laura; Heikinheimo, Liisa.

    In: Journal of Disaster Research, Vol. 5, No. 4, 2010, p. 469-478.

    Research output: Contribution to journalArticleScientificpeer-review

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    T2 - Case SCWR

    AU - Penttilä, Sami

    AU - Toivonen, Aki

    AU - Rissanen, Laura

    AU - Heikinheimo, Liisa

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    KW - creep

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