Multiaxial creep testing device for nuclear fuel claddings

Rami Pohja, Pekka Moilanen, Juhani Rantala, Santtu Huotilainen, Ville Tulkki, Ulla Ehrnstén, Stefan Holmström

    Research output: Contribution to journalArticleScientificpeer-review

    Abstract

    Mechanical properties and creep resistance are among the key issues in the selection of fuel cladding materials for future Gen-IV nuclear reactor applications. As for today's nuclear reactors, the Fukushima accident has increased the interest in accident-tolerant fuel cladding materials. Thin-walled fuel cladding tubes may exhibit anisotropic creep properties due to the manufacturing process. A newly developed Pneumatic Loading Apparatus (PLA) is capable of testing the multiaxial creep properties of thin-walled tubular specimens with internal pressure and an additional axial force. Because of its innovative design, the PLA is moveable and can be implemented in testing in extreme environments. The system functionality and accuracy was demonstrated by two biaxial creep tests performed on austenitic stainless steel DIN 1.4970 and E110 zirconium alloy specimens. Both materials showed anisotropic creep behavior and the PLA testing concept and equipment proved its capability to perform reliably and accurately biaxial creep testing of fuel cladding materials.
    Original languageEnglish
    Pages (from-to)227-240
    JournalAthens Journal of Sciences
    Volume3
    Issue number3
    Publication statusPublished - 2016
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Nuclear fuel cladding
    Creep testing
    Creep
    Pneumatics
    Nuclear reactors
    Accidents
    Testing
    Zirconium alloys
    Creep resistance
    Austenitic stainless steel
    Mechanical properties

    Keywords

    • fuel cladding
    • mechanical testing
    • multiaxial creep
    • nuclear reactor
    • pneumatic loading apparatus

    Cite this

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    title = "Multiaxial creep testing device for nuclear fuel claddings",
    abstract = "Mechanical properties and creep resistance are among the key issues in the selection of fuel cladding materials for future Gen-IV nuclear reactor applications. As for today's nuclear reactors, the Fukushima accident has increased the interest in accident-tolerant fuel cladding materials. Thin-walled fuel cladding tubes may exhibit anisotropic creep properties due to the manufacturing process. A newly developed Pneumatic Loading Apparatus (PLA) is capable of testing the multiaxial creep properties of thin-walled tubular specimens with internal pressure and an additional axial force. Because of its innovative design, the PLA is moveable and can be implemented in testing in extreme environments. The system functionality and accuracy was demonstrated by two biaxial creep tests performed on austenitic stainless steel DIN 1.4970 and E110 zirconium alloy specimens. Both materials showed anisotropic creep behavior and the PLA testing concept and equipment proved its capability to perform reliably and accurately biaxial creep testing of fuel cladding materials.",
    keywords = "fuel cladding, mechanical testing, multiaxial creep, nuclear reactor, pneumatic loading apparatus",
    author = "Rami Pohja and Pekka Moilanen and Juhani Rantala and Santtu Huotilainen and Ville Tulkki and Ulla Ehrnst{\'e}n and Stefan Holmstr{\"o}m",
    note = "SDA: SHP: SASUNE Nuclear",
    year = "2016",
    language = "English",
    volume = "3",
    pages = "227--240",
    journal = "Athens Journal of Sciences",
    issn = "2241-8466",
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    }

    Multiaxial creep testing device for nuclear fuel claddings. / Pohja, Rami; Moilanen, Pekka; Rantala, Juhani; Huotilainen, Santtu; Tulkki, Ville; Ehrnstén, Ulla; Holmström, Stefan.

    In: Athens Journal of Sciences, Vol. 3, No. 3, 2016, p. 227-240.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Multiaxial creep testing device for nuclear fuel claddings

    AU - Pohja, Rami

    AU - Moilanen, Pekka

    AU - Rantala, Juhani

    AU - Huotilainen, Santtu

    AU - Tulkki, Ville

    AU - Ehrnstén, Ulla

    AU - Holmström, Stefan

    N1 - SDA: SHP: SASUNE Nuclear

    PY - 2016

    Y1 - 2016

    N2 - Mechanical properties and creep resistance are among the key issues in the selection of fuel cladding materials for future Gen-IV nuclear reactor applications. As for today's nuclear reactors, the Fukushima accident has increased the interest in accident-tolerant fuel cladding materials. Thin-walled fuel cladding tubes may exhibit anisotropic creep properties due to the manufacturing process. A newly developed Pneumatic Loading Apparatus (PLA) is capable of testing the multiaxial creep properties of thin-walled tubular specimens with internal pressure and an additional axial force. Because of its innovative design, the PLA is moveable and can be implemented in testing in extreme environments. The system functionality and accuracy was demonstrated by two biaxial creep tests performed on austenitic stainless steel DIN 1.4970 and E110 zirconium alloy specimens. Both materials showed anisotropic creep behavior and the PLA testing concept and equipment proved its capability to perform reliably and accurately biaxial creep testing of fuel cladding materials.

    AB - Mechanical properties and creep resistance are among the key issues in the selection of fuel cladding materials for future Gen-IV nuclear reactor applications. As for today's nuclear reactors, the Fukushima accident has increased the interest in accident-tolerant fuel cladding materials. Thin-walled fuel cladding tubes may exhibit anisotropic creep properties due to the manufacturing process. A newly developed Pneumatic Loading Apparatus (PLA) is capable of testing the multiaxial creep properties of thin-walled tubular specimens with internal pressure and an additional axial force. Because of its innovative design, the PLA is moveable and can be implemented in testing in extreme environments. The system functionality and accuracy was demonstrated by two biaxial creep tests performed on austenitic stainless steel DIN 1.4970 and E110 zirconium alloy specimens. Both materials showed anisotropic creep behavior and the PLA testing concept and equipment proved its capability to perform reliably and accurately biaxial creep testing of fuel cladding materials.

    KW - fuel cladding

    KW - mechanical testing

    KW - multiaxial creep

    KW - nuclear reactor

    KW - pneumatic loading apparatus

    M3 - Article

    VL - 3

    SP - 227

    EP - 240

    JO - Athens Journal of Sciences

    JF - Athens Journal of Sciences

    SN - 2241-8466

    IS - 3

    ER -