SCC tests in SCW at 550°C on two heats of 316L

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

    Abstract

    A number of SSRT tests were performed in order to determine best behaving stainless steel for fuel cladding for supercritical water at 550oC with regards to SCC resistance. The materials were limited to austenitic stainless steels which have a code case for reactor internal applications and have a relatively good general corrosion resistance in supercritical water below 550oC. The initial results indicated that SS 316L has good enough SCC resistance, but further tests on another heat of 316L showed adverse results. The former heat showed no SCC whereas the latter heat showed very high SCC susceptibility in as-received (mill-annealed) condition, shot peened condition and in as-received condition with a TIG weld in the middle of the gauge section of the SSRT specimen. Further electrochemical testing of the degree of sensitisation revealed that the heat giving good enough SCC resistance in SSRT test was also partially sensitised.
    Original languageEnglish
    Title of host publication Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015)
    PublisherVTT Technical Research Centre of Finland
    Number of pages10
    ISBN (Electronic)978-951-38-8289-1
    ISBN (Print)978-951-38-8290-7
    Publication statusPublished - 2015
    MoE publication typeB3 Non-refereed article in conference proceedings
    Event7th International Symposium on Supercritical Water-Cooled Reactors, ISSCWR-7 - Helsinki, Finland
    Duration: 15 Mar 201518 Mar 2015

    Publication series

    SeriesVTT Technology
    Number216

    Conference

    Conference7th International Symposium on Supercritical Water-Cooled Reactors, ISSCWR-7
    Abbreviated titleISSCWR-7
    CountryFinland
    CityHelsinki
    Period15/03/1518/03/15

    Fingerprint

    Austenitic stainless steel
    Gages
    Corrosion resistance
    Water
    Welds
    Stainless steel
    Hot Temperature
    Testing

    Cite this

    Toivonen, A., Penttilä, S., & Novotny, R. (2015). SCC tests in SCW at 550°C on two heats of 316L. In Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015) [2005] VTT Technical Research Centre of Finland. VTT Technology, No. 216
    Toivonen, Aki ; Penttilä, Sami ; Novotny, Radek. / SCC tests in SCW at 550°C on two heats of 316L. Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015). VTT Technical Research Centre of Finland, 2015. (VTT Technology; No. 216).
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    title = "SCC tests in SCW at 550°C on two heats of 316L",
    abstract = "A number of SSRT tests were performed in order to determine best behaving stainless steel for fuel cladding for supercritical water at 550oC with regards to SCC resistance. The materials were limited to austenitic stainless steels which have a code case for reactor internal applications and have a relatively good general corrosion resistance in supercritical water below 550oC. The initial results indicated that SS 316L has good enough SCC resistance, but further tests on another heat of 316L showed adverse results. The former heat showed no SCC whereas the latter heat showed very high SCC susceptibility in as-received (mill-annealed) condition, shot peened condition and in as-received condition with a TIG weld in the middle of the gauge section of the SSRT specimen. Further electrochemical testing of the degree of sensitisation revealed that the heat giving good enough SCC resistance in SSRT test was also partially sensitised.",
    author = "Aki Toivonen and Sami Penttil{\"a} and Radek Novotny",
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    booktitle = "Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015)",
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    Toivonen, A, Penttilä, S & Novotny, R 2015, SCC tests in SCW at 550°C on two heats of 316L. in Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015)., 2005, VTT Technical Research Centre of Finland, VTT Technology, no. 216, 7th International Symposium on Supercritical Water-Cooled Reactors, ISSCWR-7, Helsinki, Finland, 15/03/15.

    SCC tests in SCW at 550°C on two heats of 316L. / Toivonen, Aki; Penttilä, Sami; Novotny, Radek.

    Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015). VTT Technical Research Centre of Finland, 2015. 2005 (VTT Technology; No. 216).

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

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    T1 - SCC tests in SCW at 550°C on two heats of 316L

    AU - Toivonen, Aki

    AU - Penttilä, Sami

    AU - Novotny, Radek

    N1 - HUO: USB stick

    PY - 2015

    Y1 - 2015

    N2 - A number of SSRT tests were performed in order to determine best behaving stainless steel for fuel cladding for supercritical water at 550oC with regards to SCC resistance. The materials were limited to austenitic stainless steels which have a code case for reactor internal applications and have a relatively good general corrosion resistance in supercritical water below 550oC. The initial results indicated that SS 316L has good enough SCC resistance, but further tests on another heat of 316L showed adverse results. The former heat showed no SCC whereas the latter heat showed very high SCC susceptibility in as-received (mill-annealed) condition, shot peened condition and in as-received condition with a TIG weld in the middle of the gauge section of the SSRT specimen. Further electrochemical testing of the degree of sensitisation revealed that the heat giving good enough SCC resistance in SSRT test was also partially sensitised.

    AB - A number of SSRT tests were performed in order to determine best behaving stainless steel for fuel cladding for supercritical water at 550oC with regards to SCC resistance. The materials were limited to austenitic stainless steels which have a code case for reactor internal applications and have a relatively good general corrosion resistance in supercritical water below 550oC. The initial results indicated that SS 316L has good enough SCC resistance, but further tests on another heat of 316L showed adverse results. The former heat showed no SCC whereas the latter heat showed very high SCC susceptibility in as-received (mill-annealed) condition, shot peened condition and in as-received condition with a TIG weld in the middle of the gauge section of the SSRT specimen. Further electrochemical testing of the degree of sensitisation revealed that the heat giving good enough SCC resistance in SSRT test was also partially sensitised.

    M3 - Conference article in proceedings

    SN - 978-951-38-8290-7

    T3 - VTT Technology

    BT - Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015)

    PB - VTT Technical Research Centre of Finland

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    Toivonen A, Penttilä S, Novotny R. SCC tests in SCW at 550°C on two heats of 316L. In Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015). VTT Technical Research Centre of Finland. 2015. 2005. (VTT Technology; No. 216).