Modelling of environmentally assisted cracking

Pertti Aaltonen, Timo Saario, Hannu Hänninen, Jussi Piippo, Ulla Ehrnsten, Marjo Itäaho

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

    Abstract

    During the use of nuclear reactors the properties of the structural materials change. Variations in the operation environment, such as changes in water chemistry, may enhance the development and growth of flaws. Neutron radiation causes embrittlement for in-core vessel materials. Radiation, together with water chemistry, increases the possibility of stress corrosion cracking in stainless steels and superalloys used in the reactor internal parts. Research on structural materials endeavours to study the ageing mechanisms of materials, and the possibilities and methods of preventing or forecasting the damage caused to structures by ageing.
    Original languageEnglish
    Title of host publicationRATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants
    Subtitle of host publicationSynthesis of achievements 1995-1998
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Pages125-144
    ISBN (Electronic)951-38-5264-4
    ISBN (Print)951-38-5263-6
    Publication statusPublished - 1998
    MoE publication typeA4 Article in a conference publication
    EventRATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995−1998 - Espoo, Finland
    Duration: 7 Dec 19987 Dec 1998

    Publication series

    SeriesVTT Symposium
    Number190
    ISSN0357-9387

    Conference

    ConferenceRATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants
    CountryFinland
    CityEspoo
    Period7/12/987/12/98

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