Corrosion fatigue crack growth through cladding to base metal of a CrMoV-reactor pressure vessel steel

Timo Saario, Kari Törrönen, Ralf Ahlstrand, V. Ignatov, V. Fedorova, Valeri Rybin, Boris Timofeev

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Abstract

    Corrosion fatigue crack growth rate of Soviet reactor pressure vessel steel 15X2M∅A and its cladding were studied in simulated PWR-conditions. The crack growth rate was highest in the cladding and lowest near the fusion line. No delamination or crack branching along the fusion line was found. In all cases, the ASME Code Section IX reference curves were conservative for the materials studied.
    Original languageEnglish
    Title of host publicationStructural Mechanics in Reactor Technology
    Subtitle of host publicationtransactions of the 10th International Conference
    EditorsAsadour H. Hadjian
    Place of PublicationLos Angeles
    PublisherAmerican Association for Structural Mechanics in Reactor Technology (AASMiRT)
    Pages135-139
    ISBN (Print)978-0-9623306-0-5
    Publication statusPublished - 1989
    MoE publication typeA4 Article in a conference publication
    Event10th International Conference on Structural Mechanics in Reactor Technology - Anaheim, United States
    Duration: 14 Aug 198918 Aug 1989

    Conference

    Conference10th International Conference on Structural Mechanics in Reactor Technology
    CountryUnited States
    CityAnaheim
    Period14/08/8918/08/89

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