NB-3650M fatigue calculation procedure

Paul Smeekes, Eero Torkkeli, Mårten Perklen, Otso Cronvall

    Research output: Chapter in Book/Report/Conference proceedingConference abstract in proceedingsScientific

    Abstract

    Fatigue is considered a significant long-term degradation mechanism for safety significant pressure equipment in nuclear power plants. The ASME Section III [1] procedure aims to prevent formation of fatigue cracks during the specified service period. Practical experience gathered during tens of years with hundreds of reactors has shown that the ASME methodology functions very well or is even conservative. Several studies performed in the USA and Japan indicated significant environmental effects on the fatigue as compared to fatigue without environmental effects. This has yielded a methodology as described in the NUREG/CR-6909 [2] and the JSME S NF1-2006 [17]. This methodology should obviously be applied on a best estimate fatigue analysis with reasonable safety factors. Due to the fact that such an analysis is not available and as the ASME methodology functions well this methodology is applied in conjunction with the ASME methodology. Obviously this is conservative, possibly even far overconservative. From an analytical point of view the NB3600 (engineering approach) and NB3200 (detailed 3D analysis) fatigue analysis methodology and the one in the NUREG/CR-6909 (full time history) are not compatible. In the work presented here a methodology was developed to combine these methods.
    Original languageEnglish
    Title of host publicationBaltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts
    EditorsPertti Auerkari, Juha Veivo
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Pages22
    ISBN (Electronic)978-951-38-8030-9
    ISBN (Print)978-951-38-8029-3
    Publication statusPublished - 2013
    MoE publication typeNot Eligible
    EventBALTICA IX - International Conference on Life Management and Maintenance for Power Plants - Helsinki-Stockholm, Finland
    Duration: 11 Jun 201313 Jun 2013

    Publication series

    SeriesVTT Technology
    Number107
    ISSN2242-1211

    Conference

    ConferenceBALTICA IX - International Conference on Life Management and Maintenance for Power Plants
    CountryFinland
    CityHelsinki-Stockholm
    Period11/06/1313/06/13

    Fingerprint

    Fatigue of materials
    Environmental impact
    Safety factor
    Nuclear power plants
    Degradation

    Cite this

    Smeekes, P., Torkkeli, E., Perklen, M., & Cronvall, O. (2013). NB-3650M fatigue calculation procedure. In P. Auerkari, & J. Veivo (Eds.), Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts (pp. 22). Espoo: VTT Technical Research Centre of Finland. VTT Technology, No. 107
    Smeekes, Paul ; Torkkeli, Eero ; Perklen, Mårten ; Cronvall, Otso. / NB-3650M fatigue calculation procedure. Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts. editor / Pertti Auerkari ; Juha Veivo. Espoo : VTT Technical Research Centre of Finland, 2013. pp. 22 (VTT Technology; No. 107).
    @inbook{0495688c47c742acb715131361eb50bc,
    title = "NB-3650M fatigue calculation procedure",
    abstract = "Fatigue is considered a significant long-term degradation mechanism for safety significant pressure equipment in nuclear power plants. The ASME Section III [1] procedure aims to prevent formation of fatigue cracks during the specified service period. Practical experience gathered during tens of years with hundreds of reactors has shown that the ASME methodology functions very well or is even conservative. Several studies performed in the USA and Japan indicated significant environmental effects on the fatigue as compared to fatigue without environmental effects. This has yielded a methodology as described in the NUREG/CR-6909 [2] and the JSME S NF1-2006 [17]. This methodology should obviously be applied on a best estimate fatigue analysis with reasonable safety factors. Due to the fact that such an analysis is not available and as the ASME methodology functions well this methodology is applied in conjunction with the ASME methodology. Obviously this is conservative, possibly even far overconservative. From an analytical point of view the NB3600 (engineering approach) and NB3200 (detailed 3D analysis) fatigue analysis methodology and the one in the NUREG/CR-6909 (full time history) are not compatible. In the work presented here a methodology was developed to combine these methods.",
    author = "Paul Smeekes and Eero Torkkeli and M{\aa}rten Perklen and Otso Cronvall",
    year = "2013",
    language = "English",
    isbn = "978-951-38-8029-3",
    series = "VTT Technology",
    publisher = "VTT Technical Research Centre of Finland",
    number = "107",
    pages = "22",
    editor = "Pertti Auerkari and Juha Veivo",
    booktitle = "Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts",
    address = "Finland",

    }

    Smeekes, P, Torkkeli, E, Perklen, M & Cronvall, O 2013, NB-3650M fatigue calculation procedure. in P Auerkari & J Veivo (eds), Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts. VTT Technical Research Centre of Finland, Espoo, VTT Technology, no. 107, pp. 22, BALTICA IX - International Conference on Life Management and Maintenance for Power Plants, Helsinki-Stockholm, Finland, 11/06/13.

    NB-3650M fatigue calculation procedure. / Smeekes, Paul; Torkkeli, Eero; Perklen, Mårten; Cronvall, Otso.

    Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts. ed. / Pertti Auerkari; Juha Veivo. Espoo : VTT Technical Research Centre of Finland, 2013. p. 22 (VTT Technology; No. 107).

    Research output: Chapter in Book/Report/Conference proceedingConference abstract in proceedingsScientific

    TY - CHAP

    T1 - NB-3650M fatigue calculation procedure

    AU - Smeekes, Paul

    AU - Torkkeli, Eero

    AU - Perklen, Mårten

    AU - Cronvall, Otso

    PY - 2013

    Y1 - 2013

    N2 - Fatigue is considered a significant long-term degradation mechanism for safety significant pressure equipment in nuclear power plants. The ASME Section III [1] procedure aims to prevent formation of fatigue cracks during the specified service period. Practical experience gathered during tens of years with hundreds of reactors has shown that the ASME methodology functions very well or is even conservative. Several studies performed in the USA and Japan indicated significant environmental effects on the fatigue as compared to fatigue without environmental effects. This has yielded a methodology as described in the NUREG/CR-6909 [2] and the JSME S NF1-2006 [17]. This methodology should obviously be applied on a best estimate fatigue analysis with reasonable safety factors. Due to the fact that such an analysis is not available and as the ASME methodology functions well this methodology is applied in conjunction with the ASME methodology. Obviously this is conservative, possibly even far overconservative. From an analytical point of view the NB3600 (engineering approach) and NB3200 (detailed 3D analysis) fatigue analysis methodology and the one in the NUREG/CR-6909 (full time history) are not compatible. In the work presented here a methodology was developed to combine these methods.

    AB - Fatigue is considered a significant long-term degradation mechanism for safety significant pressure equipment in nuclear power plants. The ASME Section III [1] procedure aims to prevent formation of fatigue cracks during the specified service period. Practical experience gathered during tens of years with hundreds of reactors has shown that the ASME methodology functions very well or is even conservative. Several studies performed in the USA and Japan indicated significant environmental effects on the fatigue as compared to fatigue without environmental effects. This has yielded a methodology as described in the NUREG/CR-6909 [2] and the JSME S NF1-2006 [17]. This methodology should obviously be applied on a best estimate fatigue analysis with reasonable safety factors. Due to the fact that such an analysis is not available and as the ASME methodology functions well this methodology is applied in conjunction with the ASME methodology. Obviously this is conservative, possibly even far overconservative. From an analytical point of view the NB3600 (engineering approach) and NB3200 (detailed 3D analysis) fatigue analysis methodology and the one in the NUREG/CR-6909 (full time history) are not compatible. In the work presented here a methodology was developed to combine these methods.

    M3 - Conference abstract in proceedings

    SN - 978-951-38-8029-3

    T3 - VTT Technology

    SP - 22

    BT - Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts

    A2 - Auerkari, Pertti

    A2 - Veivo, Juha

    PB - VTT Technical Research Centre of Finland

    CY - Espoo

    ER -

    Smeekes P, Torkkeli E, Perklen M, Cronvall O. NB-3650M fatigue calculation procedure. In Auerkari P, Veivo J, editors, Baltica IX. International Conference on Life Management and Maintenance for Power Plants - Abstracts. Espoo: VTT Technical Research Centre of Finland. 2013. p. 22. (VTT Technology; No. 107).