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

    Fingerprint

    water chemistry
    modeling
    growth and development
    corrosion
    vessel
    steel
    damage
    material
    radiation
    reactor
    nuclear reactor
    method

    Cite this

    Aaltonen, P., Saario, T., Hänninen, H., Piippo, J., Ehrnsten, U., & Itäaho, M. (1998). Modelling of environmentally assisted cracking. In RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998 (pp. 125-144). Espoo: VTT Technical Research Centre of Finland. VTT Symposium, No. 190
    Aaltonen, Pertti ; Saario, Timo ; Hänninen, Hannu ; Piippo, Jussi ; Ehrnsten, Ulla ; Itäaho, Marjo. / Modelling of environmentally assisted cracking. RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. Espoo : VTT Technical Research Centre of Finland, 1998. pp. 125-144 (VTT Symposium; No. 190).
    @inproceedings{061cc32feba14b5b9126a87c2a065bd0,
    title = "Modelling of environmentally assisted cracking",
    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.",
    author = "Pertti Aaltonen and Timo Saario and Hannu H{\"a}nninen and Jussi Piippo and Ulla Ehrnsten and Marjo It{\"a}aho",
    year = "1998",
    language = "English",
    isbn = "951-38-5263-6",
    series = "VTT Symposium",
    publisher = "VTT Technical Research Centre of Finland",
    number = "190",
    pages = "125--144",
    booktitle = "RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants",
    address = "Finland",

    }

    Aaltonen, P, Saario, T, Hänninen, H, Piippo, J, Ehrnsten, U & Itäaho, M 1998, Modelling of environmentally assisted cracking. in RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. VTT Technical Research Centre of Finland, Espoo, VTT Symposium, no. 190, pp. 125-144, RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants, Espoo, Finland, 7/12/98.

    Modelling of environmentally assisted cracking. / Aaltonen, Pertti; Saario, Timo; Hänninen, Hannu; Piippo, Jussi; Ehrnsten, Ulla; Itäaho, Marjo.

    RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. Espoo : VTT Technical Research Centre of Finland, 1998. p. 125-144 (VTT Symposium; No. 190).

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

    TY - GEN

    T1 - Modelling of environmentally assisted cracking

    AU - Aaltonen, Pertti

    AU - Saario, Timo

    AU - Hänninen, Hannu

    AU - Piippo, Jussi

    AU - Ehrnsten, Ulla

    AU - Itäaho, Marjo

    PY - 1998

    Y1 - 1998

    N2 - 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.

    AB - 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.

    M3 - Conference article in proceedings

    SN - 951-38-5263-6

    T3 - VTT Symposium

    SP - 125

    EP - 144

    BT - RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants

    PB - VTT Technical Research Centre of Finland

    CY - Espoo

    ER -

    Aaltonen P, Saario T, Hänninen H, Piippo J, Ehrnsten U, Itäaho M. Modelling of environmentally assisted cracking. In RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998. Espoo: VTT Technical Research Centre of Finland. 1998. p. 125-144. (VTT Symposium; No. 190).