Creep performance of fuel cladding

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

    Abstract

    The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and reliably the thermal performance and mechanical integrity of fuel rods. Fuel cladding tubes experience a range of changing conditions during their reactor life, further complicating the analysis. Today's nuclear reactors widely use zirconium alloys as fuel cladding material. Zirconium alloys exhibit anisotropic creep properties and their creep behavior depends significantly on the material condition. As for envisaged Gen-IV reactors, modified austenitic stainless steels and ODS alloys are candidate materials for claddings because of higher temperatures expected in operating conditions. This paper describes the research activities related to the creep behavior of cladding materials carried out at VTT. These activities include experimental research using the newly developed Pneumatic Loading Apparatus (PLA), which is capable of testing the steady state and transient creep properties of fuel cladding specimens with internal pressure of up to 700 bar and an additional axial force of up to 4 kN in tensile or compressive direction. Furthermore, creep models for cladding materials are being developed using viscoelastic modelling approach and Logistic Creep Strain Prediction (LCSP) method.
    Original languageEnglish
    Title of host publicationBaltica X
    Subtitle of host publicationInternational Conference on Life Management and Maintenance for Power Plants
    EditorsPertti Auerkari
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Number of pages8
    ISBN (Electronic)978-951-38-8436-9, 978-951-38-8435-2
    Publication statusPublished - 2016
    MoE publication typeA4 Article in a conference publication
    EventBALTICA X - International Conference on Life Management and Maintenance for Power Plants - Cruise, Helsinki-Stockholm, Finland
    Duration: 7 Jun 20169 Jun 2016

    Publication series

    SeriesVTT Technology
    Volume261

    Conference

    ConferenceBALTICA X - International Conference on Life Management and Maintenance for Power Plants
    Abbreviated titleBaltica X
    CountryFinland
    CityHelsinki-Stockholm
    Period7/06/169/06/16

    Fingerprint

    Creep
    Zirconium alloys
    Nuclear fuel cladding
    Nuclear reactors
    Austenitic stainless steel
    Pneumatics
    Logistics
    Testing
    Temperature

    Cite this

    Pohja, R., Tulkki, V., Ikonen, T., Moilanen, P., Rantala, J., Huotilainen, S., & Ehrnstén, U. (2016). Creep performance of fuel cladding. In P. Auerkari (Ed.), Baltica X: International Conference on Life Management and Maintenance for Power Plants Espoo: VTT Technical Research Centre of Finland. VTT Technology, Vol.. 261
    Pohja, Rami ; Tulkki, Ville ; Ikonen, Timo ; Moilanen, Pekka ; Rantala, Juhani ; Huotilainen, Santtu ; Ehrnstén, Ulla. / Creep performance of fuel cladding. Baltica X: International Conference on Life Management and Maintenance for Power Plants. editor / Pertti Auerkari. Espoo : VTT Technical Research Centre of Finland, 2016. (VTT Technology, Vol. 261).
    @inproceedings{e11a8b21df394101aa1f2923dca3b36b,
    title = "Creep performance of fuel cladding",
    abstract = "The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and reliably the thermal performance and mechanical integrity of fuel rods. Fuel cladding tubes experience a range of changing conditions during their reactor life, further complicating the analysis. Today's nuclear reactors widely use zirconium alloys as fuel cladding material. Zirconium alloys exhibit anisotropic creep properties and their creep behavior depends significantly on the material condition. As for envisaged Gen-IV reactors, modified austenitic stainless steels and ODS alloys are candidate materials for claddings because of higher temperatures expected in operating conditions. This paper describes the research activities related to the creep behavior of cladding materials carried out at VTT. These activities include experimental research using the newly developed Pneumatic Loading Apparatus (PLA), which is capable of testing the steady state and transient creep properties of fuel cladding specimens with internal pressure of up to 700 bar and an additional axial force of up to 4 kN in tensile or compressive direction. Furthermore, creep models for cladding materials are being developed using viscoelastic modelling approach and Logistic Creep Strain Prediction (LCSP) method.",
    author = "Rami Pohja and Ville Tulkki and Timo Ikonen and Pekka Moilanen and Juhani Rantala and Santtu Huotilainen and Ulla Ehrnst{\'e}n",
    year = "2016",
    language = "English",
    series = "VTT Technology",
    publisher = "VTT Technical Research Centre of Finland",
    editor = "Pertti Auerkari",
    booktitle = "Baltica X",
    address = "Finland",

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    Pohja, R, Tulkki, V, Ikonen, T, Moilanen, P, Rantala, J, Huotilainen, S & Ehrnstén, U 2016, Creep performance of fuel cladding. in P Auerkari (ed.), Baltica X: International Conference on Life Management and Maintenance for Power Plants. VTT Technical Research Centre of Finland, Espoo, VTT Technology, vol. 261, BALTICA X - International Conference on Life Management and Maintenance for Power Plants, Helsinki-Stockholm, Finland, 7/06/16.

    Creep performance of fuel cladding. / Pohja, Rami; Tulkki, Ville; Ikonen, Timo; Moilanen, Pekka; Rantala, Juhani; Huotilainen, Santtu; Ehrnstén, Ulla.

    Baltica X: International Conference on Life Management and Maintenance for Power Plants. ed. / Pertti Auerkari. Espoo : VTT Technical Research Centre of Finland, 2016. (VTT Technology, Vol. 261).

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

    TY - GEN

    T1 - Creep performance of fuel cladding

    AU - Pohja, Rami

    AU - Tulkki, Ville

    AU - Ikonen, Timo

    AU - Moilanen, Pekka

    AU - Rantala, Juhani

    AU - Huotilainen, Santtu

    AU - Ehrnstén, Ulla

    PY - 2016

    Y1 - 2016

    N2 - The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and reliably the thermal performance and mechanical integrity of fuel rods. Fuel cladding tubes experience a range of changing conditions during their reactor life, further complicating the analysis. Today's nuclear reactors widely use zirconium alloys as fuel cladding material. Zirconium alloys exhibit anisotropic creep properties and their creep behavior depends significantly on the material condition. As for envisaged Gen-IV reactors, modified austenitic stainless steels and ODS alloys are candidate materials for claddings because of higher temperatures expected in operating conditions. This paper describes the research activities related to the creep behavior of cladding materials carried out at VTT. These activities include experimental research using the newly developed Pneumatic Loading Apparatus (PLA), which is capable of testing the steady state and transient creep properties of fuel cladding specimens with internal pressure of up to 700 bar and an additional axial force of up to 4 kN in tensile or compressive direction. Furthermore, creep models for cladding materials are being developed using viscoelastic modelling approach and Logistic Creep Strain Prediction (LCSP) method.

    AB - The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and reliably the thermal performance and mechanical integrity of fuel rods. Fuel cladding tubes experience a range of changing conditions during their reactor life, further complicating the analysis. Today's nuclear reactors widely use zirconium alloys as fuel cladding material. Zirconium alloys exhibit anisotropic creep properties and their creep behavior depends significantly on the material condition. As for envisaged Gen-IV reactors, modified austenitic stainless steels and ODS alloys are candidate materials for claddings because of higher temperatures expected in operating conditions. This paper describes the research activities related to the creep behavior of cladding materials carried out at VTT. These activities include experimental research using the newly developed Pneumatic Loading Apparatus (PLA), which is capable of testing the steady state and transient creep properties of fuel cladding specimens with internal pressure of up to 700 bar and an additional axial force of up to 4 kN in tensile or compressive direction. Furthermore, creep models for cladding materials are being developed using viscoelastic modelling approach and Logistic Creep Strain Prediction (LCSP) method.

    M3 - Conference article in proceedings

    T3 - VTT Technology

    BT - Baltica X

    A2 - Auerkari, Pertti

    PB - VTT Technical Research Centre of Finland

    CY - Espoo

    ER -

    Pohja R, Tulkki V, Ikonen T, Moilanen P, Rantala J, Huotilainen S et al. Creep performance of fuel cladding. In Auerkari P, editor, Baltica X: International Conference on Life Management and Maintenance for Power Plants. Espoo: VTT Technical Research Centre of Finland. 2016. (VTT Technology, Vol. 261).