Stress corrosion cracking susceptibility of austenitic stainless steels in supercritical water conditions

R. Novotny (Corresponding Author), P. Hähner, J. Siegl, P. Hausild, S. Ripplinger, Sami Penttilä, Aki Toivonen

    Research output: Contribution to journalArticleScientificpeer-review

    43 Citations (Scopus)

    Abstract

    The presented paper summarizes the results of general corrosion and stress corrosion cracking (SCC) susceptibility tests in supercritical water (SCW), studied for austenitic stainless steel 316L, with the aim to identify maximum SCW temperature usability and specific failure mechanisms prevailing during slow strain-rate tensile (SSRT) tests in ultra-pure demineralized SCW solution with controlled oxygen content. The general corrosion tests clearly revealed the applicability of austenitic stainless steel in SCW to be limited to 550 °C as maximum temperature as oxidation rates of austenitic stainless steels 316L increase dramatically above 550 °C. The SSRT tests were performed using a step-motor controlled loading device in an autoclave at 550 °C SCW. Besides the strain rate (resp. crosshead speed), the oxygen content was varied in the series of tests. The obtained results showed that even at the lowest strain rate, a serious increase of SCC susceptibility, as typically characterized by IGSCC crack growth, was not observed. The fractography confirmed that failure was due to a combination of transgranular SCC and transgranular ductile fracture. Based on fractographic findings a phenomenological map describing the SCC regime of SSRT test parameters could be proposed for AISI 316L.
    Original languageEnglish
    Pages (from-to)117-123
    Number of pages7
    JournalJournal of Nuclear Materials
    Volume409
    Issue number2
    DOIs
    Publication statusPublished - 2010
    MoE publication typeA1 Journal article-refereed
    EventIAEA-EC Topical Meeting on Development of New Structural Materials for Advanced Fission and Fusion Reactor Materials, TR-37435 - Barcelona, Spain
    Duration: 5 Oct 20099 Oct 2009

    Fingerprint

    stress corrosion cracking
    austenitic stainless steels
    Stress corrosion cracking
    Austenitic stainless steel
    strain rate
    Strain rate
    magnetic permeability
    tensile tests
    Water
    water
    transgranular corrosion
    corrosion
    Corrosion
    fractography
    Oxygen
    corrosion tests
    Fractography
    Stepping motors
    autoclaves
    water temperature

    Keywords

    • SCW
    • Corrosion
    • SCC
    • SSRT
    • general corrosion

    Cite this

    Novotny, R. ; Hähner, P. ; Siegl, J. ; Hausild, P. ; Ripplinger, S. ; Penttilä, Sami ; Toivonen, Aki. / Stress corrosion cracking susceptibility of austenitic stainless steels in supercritical water conditions. In: Journal of Nuclear Materials. 2010 ; Vol. 409, No. 2. pp. 117-123.
    @article{6b043e73a37f477eb1a7a8f4b01fbf31,
    title = "Stress corrosion cracking susceptibility of austenitic stainless steels in supercritical water conditions",
    abstract = "The presented paper summarizes the results of general corrosion and stress corrosion cracking (SCC) susceptibility tests in supercritical water (SCW), studied for austenitic stainless steel 316L, with the aim to identify maximum SCW temperature usability and specific failure mechanisms prevailing during slow strain-rate tensile (SSRT) tests in ultra-pure demineralized SCW solution with controlled oxygen content. The general corrosion tests clearly revealed the applicability of austenitic stainless steel in SCW to be limited to 550 °C as maximum temperature as oxidation rates of austenitic stainless steels 316L increase dramatically above 550 °C. The SSRT tests were performed using a step-motor controlled loading device in an autoclave at 550 °C SCW. Besides the strain rate (resp. crosshead speed), the oxygen content was varied in the series of tests. The obtained results showed that even at the lowest strain rate, a serious increase of SCC susceptibility, as typically characterized by IGSCC crack growth, was not observed. The fractography confirmed that failure was due to a combination of transgranular SCC and transgranular ductile fracture. Based on fractographic findings a phenomenological map describing the SCC regime of SSRT test parameters could be proposed for AISI 316L.",
    keywords = "SCW, Corrosion, SCC, SSRT, general corrosion",
    author = "R. Novotny and P. H{\"a}hner and J. Siegl and P. Hausild and S. Ripplinger and Sami Penttil{\"a} and Aki Toivonen",
    note = "Project code: 20062",
    year = "2010",
    doi = "10.1016/j.jnucmat.2010.09.018",
    language = "English",
    volume = "409",
    pages = "117--123",
    journal = "Journal of Nuclear Materials",
    issn = "0022-3115",
    publisher = "Elsevier",
    number = "2",

    }

    Stress corrosion cracking susceptibility of austenitic stainless steels in supercritical water conditions. / Novotny, R. (Corresponding Author); Hähner, P.; Siegl, J.; Hausild, P.; Ripplinger, S.; Penttilä, Sami; Toivonen, Aki.

    In: Journal of Nuclear Materials, Vol. 409, No. 2, 2010, p. 117-123.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Stress corrosion cracking susceptibility of austenitic stainless steels in supercritical water conditions

    AU - Novotny, R.

    AU - Hähner, P.

    AU - Siegl, J.

    AU - Hausild, P.

    AU - Ripplinger, S.

    AU - Penttilä, Sami

    AU - Toivonen, Aki

    N1 - Project code: 20062

    PY - 2010

    Y1 - 2010

    N2 - The presented paper summarizes the results of general corrosion and stress corrosion cracking (SCC) susceptibility tests in supercritical water (SCW), studied for austenitic stainless steel 316L, with the aim to identify maximum SCW temperature usability and specific failure mechanisms prevailing during slow strain-rate tensile (SSRT) tests in ultra-pure demineralized SCW solution with controlled oxygen content. The general corrosion tests clearly revealed the applicability of austenitic stainless steel in SCW to be limited to 550 °C as maximum temperature as oxidation rates of austenitic stainless steels 316L increase dramatically above 550 °C. The SSRT tests were performed using a step-motor controlled loading device in an autoclave at 550 °C SCW. Besides the strain rate (resp. crosshead speed), the oxygen content was varied in the series of tests. The obtained results showed that even at the lowest strain rate, a serious increase of SCC susceptibility, as typically characterized by IGSCC crack growth, was not observed. The fractography confirmed that failure was due to a combination of transgranular SCC and transgranular ductile fracture. Based on fractographic findings a phenomenological map describing the SCC regime of SSRT test parameters could be proposed for AISI 316L.

    AB - The presented paper summarizes the results of general corrosion and stress corrosion cracking (SCC) susceptibility tests in supercritical water (SCW), studied for austenitic stainless steel 316L, with the aim to identify maximum SCW temperature usability and specific failure mechanisms prevailing during slow strain-rate tensile (SSRT) tests in ultra-pure demineralized SCW solution with controlled oxygen content. The general corrosion tests clearly revealed the applicability of austenitic stainless steel in SCW to be limited to 550 °C as maximum temperature as oxidation rates of austenitic stainless steels 316L increase dramatically above 550 °C. The SSRT tests were performed using a step-motor controlled loading device in an autoclave at 550 °C SCW. Besides the strain rate (resp. crosshead speed), the oxygen content was varied in the series of tests. The obtained results showed that even at the lowest strain rate, a serious increase of SCC susceptibility, as typically characterized by IGSCC crack growth, was not observed. The fractography confirmed that failure was due to a combination of transgranular SCC and transgranular ductile fracture. Based on fractographic findings a phenomenological map describing the SCC regime of SSRT test parameters could be proposed for AISI 316L.

    KW - SCW

    KW - Corrosion

    KW - SCC

    KW - SSRT

    KW - general corrosion

    U2 - 10.1016/j.jnucmat.2010.09.018

    DO - 10.1016/j.jnucmat.2010.09.018

    M3 - Article

    VL - 409

    SP - 117

    EP - 123

    JO - Journal of Nuclear Materials

    JF - Journal of Nuclear Materials

    SN - 0022-3115

    IS - 2

    ER -