Volume 7, Issue 8 (September 2010)

    REFLET Experiment in OSIRIS: Relaxation under Flux as a Method for Determining Creep Behavior of Zircaloy Assembly Components

    (Received 16 March 2010; accepted 24 June 2010)

    Published Online: 2010

    CODEN: JAIOAD

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    Abstract

    A stress relaxation on bent-beam specimen irradiation campaign was performed in the French material testing reactor OSIRIS in order to screen different materials according to their in-flux behavior and to derive constitutive laws that are used to describe the in-reactor behavior of assembly components under axial stress. This paper presents the methodology used, with particular emphasis on the validation of the different hypotheses. The methodology is illustrated with the results obtained on an industrial Zircaloy-4 (Zy-4) alloy used in guide thimbles. As an illustration of the capability of the method, the parameters of simple creep behavior laws are adjusted to the relaxation results. The creep-law predictions are compared to results obtained previously in a creep experiment.


    Author Information:

    Carassou, S.
    Nuclear Energy Division, CEA Saclay, Gif-sur-Yvette,

    Duguay, C.
    Nuclear Energy Division, CEA Cadarache, Saint Paul Lez Durance Cedex,

    Yvon, P.
    Nuclear Energy Division, CEA Saclay, Gif-sur-Yvette,

    Rozenblum, F.
    Nuclear Energy Division, CEA Saclay, Gif-sur-Yvette,

    Cloué, J. M.
    AREVA, AREVA NP SAS, Lyon Cedex 6,

    Chabretou, V.
    AREVA, AREVA NP SAS, Lyon Cedex 6,

    Bernaudat, C.
    SEPTEN, EDF, Villeurbanne Cedex,

    Levasseur, B.
    SEPTEN, EDF, Villeurbanne Cedex,

    Maurice, A.
    SEPTEN, EDF, Villeurbanne Cedex,

    Bouffioux, P.
    DRD/MMC, EDF, Moret sur Loing Cedex, Site des Renardières

    Audic, K.
    DRD/MMC, EDF, Moret sur Loing Cedex, Site des Renardières


    Stock #: JAI103065

    ISSN: 1546-962X

    DOI: 10.1520/JAI103065

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    Author
    Title REFLET Experiment in OSIRIS: Relaxation under Flux as a Method for Determining Creep Behavior of Zircaloy Assembly Components
    Symposium Zirconium in the Nuclear Industry, 0000-00-00
    Committee B10