Candidate materials performance under Supercritical Water Reactor (SCWR) conditions

Aki Toivonen, Sami Penttilä, Laura Rissanen

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

    Abstract

    The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and a core coolant temperature up to 500°C. As an evolutionary step this reactor type follows the development path of modern supercritical coal-fired plants. This paper reviews the results on performance of commercial candidate materials for in-core applications focusing on corrosion, stress corrosion cracking (SCC) and creep issues. General corrosion (oxidation) tests with an inlet oxygen concentration of 125-150 ppb have been performed on several iron and nickel alloys at 300 to 650°C and 25 MPa in supercritical water. Stress corrosion cracking (SCC) susceptibility of selected austenitic stainless steels and a high chromium ODS (Oxide Dispersion Strengthened) alloy were also studied in slow strain rate tests (SSRT) in supercritical water at 500°C and 650°C. Furthermore, constant load creep tests have been performed on selected austenitic steels at 500°C and 650°C in supercritical water (25 MPa, 1 ppm O2) and in an inert atmosphere (He, pressure 1 atm). Based on the materials studies, the current candidate materials for the core internals are austenitic steels with sufficient oxidation and creep resistance up to 500-550°C. High chromium austenitic steels and ODS alloys steels are considered for the fuel rod cladding due to their oxidation resistance up to 650°C. However, problems with manufacturing and joining of ODS alloys need to be solved. Alloys with high nickel content were not considered for the SCC or creep studies because of the strong effect of Ni on neutronics of the reactor core.
    Original languageEnglish
    Title of host publicationBaltica VIII
    Subtitle of host publicationLife Management and Maintenance for Power Plants
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Pages351-371
    Volume1
    ISBN (Electronic)978-951-38-7592-3
    ISBN (Print)978-951-38-7591-6
    Publication statusPublished - 2010
    MoE publication typeB3 Non-refereed article in conference proceedings
    EventBALTICA VIII - International Conference on Life Management and Maintenance for Power Plants - Helsinki-Stockholm, Finland
    Duration: 18 May 201020 May 2010

    Publication series

    SeriesVTT Symposium
    Number264
    ISSN0357-9387

    Conference

    ConferenceBALTICA VIII - International Conference on Life Management and Maintenance for Power Plants
    CountryFinland
    CityHelsinki-Stockholm
    Period18/05/1020/05/10

    Fingerprint

    Austenitic steel
    Stress corrosion cracking
    Creep
    Oxidation resistance
    Oxides
    Chromium
    Corrosion
    Water
    Creep resistance
    Light water reactors
    Reactor cores
    Iron alloys
    Nickel alloys
    Alloy steel
    Austenitic stainless steel
    Joining
    Coolants
    Strain rate
    Nickel
    Coal

    Cite this

    Toivonen, A., Penttilä, S., & Rissanen, L. (2010). Candidate materials performance under Supercritical Water Reactor (SCWR) conditions. In Baltica VIII: Life Management and Maintenance for Power Plants (Vol. 1, pp. 351-371). Espoo: VTT Technical Research Centre of Finland. VTT Symposium, No. 264
    Toivonen, Aki ; Penttilä, Sami ; Rissanen, Laura. / Candidate materials performance under Supercritical Water Reactor (SCWR) conditions. Baltica VIII: Life Management and Maintenance for Power Plants. Vol. 1 Espoo : VTT Technical Research Centre of Finland, 2010. pp. 351-371 (VTT Symposium; No. 264).
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    abstract = "The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and a core coolant temperature up to 500°C. As an evolutionary step this reactor type follows the development path of modern supercritical coal-fired plants. This paper reviews the results on performance of commercial candidate materials for in-core applications focusing on corrosion, stress corrosion cracking (SCC) and creep issues. General corrosion (oxidation) tests with an inlet oxygen concentration of 125-150 ppb have been performed on several iron and nickel alloys at 300 to 650°C and 25 MPa in supercritical water. Stress corrosion cracking (SCC) susceptibility of selected austenitic stainless steels and a high chromium ODS (Oxide Dispersion Strengthened) alloy were also studied in slow strain rate tests (SSRT) in supercritical water at 500°C and 650°C. Furthermore, constant load creep tests have been performed on selected austenitic steels at 500°C and 650°C in supercritical water (25 MPa, 1 ppm O2) and in an inert atmosphere (He, pressure 1 atm). Based on the materials studies, the current candidate materials for the core internals are austenitic steels with sufficient oxidation and creep resistance up to 500-550°C. High chromium austenitic steels and ODS alloys steels are considered for the fuel rod cladding due to their oxidation resistance up to 650°C. However, problems with manufacturing and joining of ODS alloys need to be solved. Alloys with high nickel content were not considered for the SCC or creep studies because of the strong effect of Ni on neutronics of the reactor core.",
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    Toivonen, A, Penttilä, S & Rissanen, L 2010, Candidate materials performance under Supercritical Water Reactor (SCWR) conditions. in Baltica VIII: Life Management and Maintenance for Power Plants. vol. 1, VTT Technical Research Centre of Finland, Espoo, VTT Symposium, no. 264, pp. 351-371, BALTICA VIII - International Conference on Life Management and Maintenance for Power Plants, Helsinki-Stockholm, Finland, 18/05/10.

    Candidate materials performance under Supercritical Water Reactor (SCWR) conditions. / Toivonen, Aki; Penttilä, Sami; Rissanen, Laura.

    Baltica VIII: Life Management and Maintenance for Power Plants. Vol. 1 Espoo : VTT Technical Research Centre of Finland, 2010. p. 351-371 (VTT Symposium; No. 264).

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

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    T1 - Candidate materials performance under Supercritical Water Reactor (SCWR) conditions

    AU - Toivonen, Aki

    AU - Penttilä, Sami

    AU - Rissanen, Laura

    PY - 2010

    Y1 - 2010

    N2 - The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and a core coolant temperature up to 500°C. As an evolutionary step this reactor type follows the development path of modern supercritical coal-fired plants. This paper reviews the results on performance of commercial candidate materials for in-core applications focusing on corrosion, stress corrosion cracking (SCC) and creep issues. General corrosion (oxidation) tests with an inlet oxygen concentration of 125-150 ppb have been performed on several iron and nickel alloys at 300 to 650°C and 25 MPa in supercritical water. Stress corrosion cracking (SCC) susceptibility of selected austenitic stainless steels and a high chromium ODS (Oxide Dispersion Strengthened) alloy were also studied in slow strain rate tests (SSRT) in supercritical water at 500°C and 650°C. Furthermore, constant load creep tests have been performed on selected austenitic steels at 500°C and 650°C in supercritical water (25 MPa, 1 ppm O2) and in an inert atmosphere (He, pressure 1 atm). Based on the materials studies, the current candidate materials for the core internals are austenitic steels with sufficient oxidation and creep resistance up to 500-550°C. High chromium austenitic steels and ODS alloys steels are considered for the fuel rod cladding due to their oxidation resistance up to 650°C. However, problems with manufacturing and joining of ODS alloys need to be solved. Alloys with high nickel content were not considered for the SCC or creep studies because of the strong effect of Ni on neutronics of the reactor core.

    AB - The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and a core coolant temperature up to 500°C. As an evolutionary step this reactor type follows the development path of modern supercritical coal-fired plants. This paper reviews the results on performance of commercial candidate materials for in-core applications focusing on corrosion, stress corrosion cracking (SCC) and creep issues. General corrosion (oxidation) tests with an inlet oxygen concentration of 125-150 ppb have been performed on several iron and nickel alloys at 300 to 650°C and 25 MPa in supercritical water. Stress corrosion cracking (SCC) susceptibility of selected austenitic stainless steels and a high chromium ODS (Oxide Dispersion Strengthened) alloy were also studied in slow strain rate tests (SSRT) in supercritical water at 500°C and 650°C. Furthermore, constant load creep tests have been performed on selected austenitic steels at 500°C and 650°C in supercritical water (25 MPa, 1 ppm O2) and in an inert atmosphere (He, pressure 1 atm). Based on the materials studies, the current candidate materials for the core internals are austenitic steels with sufficient oxidation and creep resistance up to 500-550°C. High chromium austenitic steels and ODS alloys steels are considered for the fuel rod cladding due to their oxidation resistance up to 650°C. However, problems with manufacturing and joining of ODS alloys need to be solved. Alloys with high nickel content were not considered for the SCC or creep studies because of the strong effect of Ni on neutronics of the reactor core.

    M3 - Conference article in proceedings

    SN - 978-951-38-7591-6

    VL - 1

    T3 - VTT Symposium

    SP - 351

    EP - 371

    BT - Baltica VIII

    PB - VTT Technical Research Centre of Finland

    CY - Espoo

    ER -

    Toivonen A, Penttilä S, Rissanen L. Candidate materials performance under Supercritical Water Reactor (SCWR) conditions. In Baltica VIII: Life Management and Maintenance for Power Plants. Vol. 1. Espoo: VTT Technical Research Centre of Finland. 2010. p. 351-371. (VTT Symposium; No. 264).