European Project "Supercritical Water Reactor: Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests

Radek Novotny, Premysl Janík, Aki Toivonen, Anna Ruiz, Zoltan Szaraz, Jan Siegl, Petr Hausild, Sami Penttilä

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

    Abstract

    The main target of the HPLWR Phase 2 follow-up FP7 project “Fuel Qualification Test for Super Critical Water Reactor” is to make significant progress towards the design, analysis and licensing of a fuel assembly cooled with supercritical water in a research reactor which also includes the material research on those in-core materials which could be licensed in near future. In frame of WP4 - Pre-qualification, stress corrosion cracking (SCC) resistance of three selected austenitic stainless steels 08Cr18Ni10Ti (equivalent of AISI 321), AISI 347H and AISI 316L was investigated by conducting slow strain rate tensile tests in an autoclave in 550°C supercritical water. SCC susceptibility was evaluated using three criteria: loss of mechanical properties compared to those in inert environment, fractographic analysis of the fracture surfaces and finally analysis of secondary cracks. Obtained results were compared to those available in the literature and utilization of these results is discussed. Based on the results of SSRT tests and following fractographic analysis, 316L was selected as the best performer.
    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 pages15
    EditionUSB stick
    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

    Stress corrosion cracking
    Water
    Research reactors
    Autoclaves
    Austenitic stainless steel
    Strain rate
    Cracks
    Mechanical properties

    Cite this

    Novotny, R., Janík, P., Toivonen, A., Ruiz, A., Szaraz, Z., Siegl, J., ... Penttilä, S. (2015). European Project "Supercritical Water Reactor: Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests. In Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015) (USB stick ed.). [2078] VTT Technical Research Centre of Finland. VTT Technology, No. 216
    Novotny, Radek ; Janík, Premysl ; Toivonen, Aki ; Ruiz, Anna ; Szaraz, Zoltan ; Siegl, Jan ; Hausild, Petr ; Penttilä, Sami. / European Project "Supercritical Water Reactor : Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests. Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015). USB stick. ed. VTT Technical Research Centre of Finland, 2015. (VTT Technology; No. 216).
    @inproceedings{8324ed215c7d4e7b9847782aa9faabf5,
    title = "European Project {"}Supercritical Water Reactor: Fuel Qualification Test{"} (SCWR-FQT): Results of SCC susceptibility tests",
    abstract = "The main target of the HPLWR Phase 2 follow-up FP7 project “Fuel Qualification Test for Super Critical Water Reactor” is to make significant progress towards the design, analysis and licensing of a fuel assembly cooled with supercritical water in a research reactor which also includes the material research on those in-core materials which could be licensed in near future. In frame of WP4 - Pre-qualification, stress corrosion cracking (SCC) resistance of three selected austenitic stainless steels 08Cr18Ni10Ti (equivalent of AISI 321), AISI 347H and AISI 316L was investigated by conducting slow strain rate tensile tests in an autoclave in 550°C supercritical water. SCC susceptibility was evaluated using three criteria: loss of mechanical properties compared to those in inert environment, fractographic analysis of the fracture surfaces and finally analysis of secondary cracks. Obtained results were compared to those available in the literature and utilization of these results is discussed. Based on the results of SSRT tests and following fractographic analysis, 316L was selected as the best performer.",
    author = "Radek Novotny and Premysl Jan{\'i}k and Aki Toivonen and Anna Ruiz and Zoltan Szaraz and Jan Siegl and Petr Hausild and Sami Penttil{\"a}",
    year = "2015",
    language = "English",
    isbn = "978-951-38-8290-7",
    series = "VTT Technology",
    publisher = "VTT Technical Research Centre of Finland",
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    booktitle = "Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015)",
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    Novotny, R, Janík, P, Toivonen, A, Ruiz, A, Szaraz, Z, Siegl, J, Hausild, P & Penttilä, S 2015, European Project "Supercritical Water Reactor: Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests. in Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015). USB stick edn, 2078, 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.

    European Project "Supercritical Water Reactor : Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests. / Novotny, Radek; Janík, Premysl; Toivonen, Aki; Ruiz, Anna; Szaraz, Zoltan; Siegl, Jan; Hausild, Petr; Penttilä, Sami.

    Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015). USB stick. ed. VTT Technical Research Centre of Finland, 2015. 2078 (VTT Technology; No. 216).

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

    TY - GEN

    T1 - European Project "Supercritical Water Reactor

    T2 - Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests

    AU - Novotny, Radek

    AU - Janík, Premysl

    AU - Toivonen, Aki

    AU - Ruiz, Anna

    AU - Szaraz, Zoltan

    AU - Siegl, Jan

    AU - Hausild, Petr

    AU - Penttilä, Sami

    PY - 2015

    Y1 - 2015

    N2 - The main target of the HPLWR Phase 2 follow-up FP7 project “Fuel Qualification Test for Super Critical Water Reactor” is to make significant progress towards the design, analysis and licensing of a fuel assembly cooled with supercritical water in a research reactor which also includes the material research on those in-core materials which could be licensed in near future. In frame of WP4 - Pre-qualification, stress corrosion cracking (SCC) resistance of three selected austenitic stainless steels 08Cr18Ni10Ti (equivalent of AISI 321), AISI 347H and AISI 316L was investigated by conducting slow strain rate tensile tests in an autoclave in 550°C supercritical water. SCC susceptibility was evaluated using three criteria: loss of mechanical properties compared to those in inert environment, fractographic analysis of the fracture surfaces and finally analysis of secondary cracks. Obtained results were compared to those available in the literature and utilization of these results is discussed. Based on the results of SSRT tests and following fractographic analysis, 316L was selected as the best performer.

    AB - The main target of the HPLWR Phase 2 follow-up FP7 project “Fuel Qualification Test for Super Critical Water Reactor” is to make significant progress towards the design, analysis and licensing of a fuel assembly cooled with supercritical water in a research reactor which also includes the material research on those in-core materials which could be licensed in near future. In frame of WP4 - Pre-qualification, stress corrosion cracking (SCC) resistance of three selected austenitic stainless steels 08Cr18Ni10Ti (equivalent of AISI 321), AISI 347H and AISI 316L was investigated by conducting slow strain rate tensile tests in an autoclave in 550°C supercritical water. SCC susceptibility was evaluated using three criteria: loss of mechanical properties compared to those in inert environment, fractographic analysis of the fracture surfaces and finally analysis of secondary cracks. Obtained results were compared to those available in the literature and utilization of these results is discussed. Based on the results of SSRT tests and following fractographic analysis, 316L was selected as the best performer.

    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

    ER -

    Novotny R, Janík P, Toivonen A, Ruiz A, Szaraz Z, Siegl J et al. European Project "Supercritical Water Reactor: Fuel Qualification Test" (SCWR-FQT): Results of SCC susceptibility tests. In Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR 2015). USB stick ed. VTT Technical Research Centre of Finland. 2015. 2078. (VTT Technology; No. 216).