Ageing phenomena (AGE): Ageing and oxidation of reactor materials

Pertti Aaltonen, Petri Kinnunen, Päivi Karjalainen-Roikonen, Timo Laitinen, Lena Hansson, Matti Valo

    Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

    Abstract

    The target of this project has been to study and model the changing properties of ageing pressure boundary materials used in nuclear power plants. Models to estimate and methods to measure the behaviour of these materials under various operational conditions in nuclear power plants have been developed and applied. In nuclear reactors stainless steels are mainly used as a material facing the primary circuit environment. Thus, the main focus has been to study the role of the primary circuit environment and surface oxide films containing Fe, Ni and Cr on changes occurring in the mechanical properties and degradation susceptibility of ageing pressure boundary materials.
    Original languageEnglish
    Title of host publicationFINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002
    Subtitle of host publicationFinal Report
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Pages38-51
    ISBN (Electronic)951-38-6086-8
    ISBN (Print)951-38-6085-X
    Publication statusPublished - 2002
    MoE publication typeNot Eligible

    Publication series

    SeriesVTT Tiedotteita - Research Notes
    Number2164
    ISSN1235-0605

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  • Cite this

    Aaltonen, P., Kinnunen, P., Karjalainen-Roikonen, P., Laitinen, T., Hansson, L., & Valo, M. (2002). Ageing phenomena (AGE): Ageing and oxidation of reactor materials. In FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002: Final Report (pp. 38-51). VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2164 http://www.vtt.fi/inf/pdf/tiedotteet/2002/T2164.pdf