Method development for studies of environmentally assisted cracking (EAC)

Päivi Karjalainen-Roikonen, Pekka Moilanen, Aki Toivonen, Pertti Aaltonen

    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. The objective within the subproject "Material degradation due to corrosive environment" of the RATU2 project was to evaluate the factors affecting the changes in material properties due to the environment and stresses, and to assess their interrelationship. The subproject included among others the following tasks: · Development of routine EAC crack growth testing method for small test specimens. · Application of rising displacement testing to study irradiation assisted stress corrosion cracking (IASCC). New simplified techniques for determination of fracture resistance curves in simulated reactor environments. Multi-specimen bellows loading system to provide more experimental EAC data than can be obtained with previous servo hydraulic or mechanical loading systems.
    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
    Pages105-124
    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

    Stress corrosion cracking
    Aging of materials
    Radiation
    Bellows
    Testing
    Embrittlement
    Nuclear reactors
    Superalloys
    Fracture toughness
    Water
    Crack propagation
    Materials properties
    Neutrons
    Stainless steel
    Hydraulics
    Irradiation
    Degradation
    Defects

    Cite this

    Karjalainen-Roikonen, P., Moilanen, P., Toivonen, A., & Aaltonen, P. (1998). Method development for studies of environmentally assisted cracking (EAC). In RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants: Synthesis of achievements 1995-1998 (pp. 105-124). Espoo: VTT Technical Research Centre of Finland. VTT Symposium, No. 190
    Karjalainen-Roikonen, Päivi ; Moilanen, Pekka ; Toivonen, Aki ; Aaltonen, Pertti. / Method development for studies of environmentally assisted cracking (EAC). 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. 105-124 (VTT Symposium; No. 190).
    @inproceedings{a3089bce18dd41d2912a04e2e828a466,
    title = "Method development for studies of environmentally assisted cracking (EAC)",
    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. The objective within the subproject {"}Material degradation due to corrosive environment{"} of the RATU2 project was to evaluate the factors affecting the changes in material properties due to the environment and stresses, and to assess their interrelationship. The subproject included among others the following tasks: · Development of routine EAC crack growth testing method for small test specimens. · Application of rising displacement testing to study irradiation assisted stress corrosion cracking (IASCC). New simplified techniques for determination of fracture resistance curves in simulated reactor environments. Multi-specimen bellows loading system to provide more experimental EAC data than can be obtained with previous servo hydraulic or mechanical loading systems.",
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    year = "1998",
    language = "English",
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    series = "VTT Symposium",
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    Karjalainen-Roikonen, P, Moilanen, P, Toivonen, A & Aaltonen, P 1998, Method development for studies of environmentally assisted cracking (EAC). 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. 105-124, RATU2: The Finnish Research Programme on the Structural Integrity of Nuclear Power Plants, Espoo, Finland, 7/12/98.

    Method development for studies of environmentally assisted cracking (EAC). / Karjalainen-Roikonen, Päivi; Moilanen, Pekka; Toivonen, Aki; Aaltonen, Pertti.

    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. 105-124 (VTT Symposium; No. 190).

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

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    AU - Aaltonen, Pertti

    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. The objective within the subproject "Material degradation due to corrosive environment" of the RATU2 project was to evaluate the factors affecting the changes in material properties due to the environment and stresses, and to assess their interrelationship. The subproject included among others the following tasks: · Development of routine EAC crack growth testing method for small test specimens. · Application of rising displacement testing to study irradiation assisted stress corrosion cracking (IASCC). New simplified techniques for determination of fracture resistance curves in simulated reactor environments. Multi-specimen bellows loading system to provide more experimental EAC data than can be obtained with previous servo hydraulic or mechanical loading systems.

    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. The objective within the subproject "Material degradation due to corrosive environment" of the RATU2 project was to evaluate the factors affecting the changes in material properties due to the environment and stresses, and to assess their interrelationship. The subproject included among others the following tasks: · Development of routine EAC crack growth testing method for small test specimens. · Application of rising displacement testing to study irradiation assisted stress corrosion cracking (IASCC). New simplified techniques for determination of fracture resistance curves in simulated reactor environments. Multi-specimen bellows loading system to provide more experimental EAC data than can be obtained with previous servo hydraulic or mechanical loading systems.

    M3 - Conference article in proceedings

    SN - 951-38-5263-6

    T3 - VTT Symposium

    SP - 105

    EP - 124

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

    PB - VTT Technical Research Centre of Finland

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    ER -

    Karjalainen-Roikonen P, Moilanen P, Toivonen A, Aaltonen P. Method development for studies of environmentally assisted cracking (EAC). 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. 105-124. (VTT Symposium; No. 190).