Volume 2, Issue 6 (June 2005)

    Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior

    (Received 15 March 2004; accepted 6 December 2004)

    Published Online: 2005

    CODEN: JAIOAD

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    Abstract

    The PROMETRA material testing program is a support program related to the study of high burnup fuel rod behavior under Reactivity Initiated Accidents (RIA) and to the interpretation of the CABRI REP-Na RIA test results. Hoop and axial tensile tests have been performed on fresh and irradiated Zircaloy-4 cladding alloy first at CEA Grenoble hot labs and now at CEA Saclay in order to assess the cladding mechanical behavior during RIA transients. Efforts have been continuously carried out in order to improve the prototipicallity of the tests for RIA studies involving new specimens and new testing techniques. The corrosion level of irradiated specimens reached up to 130 μm of oxide layer thickness. The influence of in-pile oxide layer spallation has also been addressed. High strain-rate material properties of irradiated Zircaloy-4 and the consequences of hydride embrittlement can be derived from the PROMETRA program.


    Author Information:

    Desquines, J
    Research Engineer, IRSN, DPAM/SEMCA, Saint Paul-Lez-Durance,

    Cazalis, B
    Research Engineer, IRSN, DPAM/SEMCA, Saint Paul-Lez-Durance,

    Bernaudat, C
    Consulting Engineer, EDF-SEPTEN, Villeurbanne Cedex,

    Poussard, C
    Research Engineer, CEA-Saclay, DEN/DMN/SEMI, Gif Sur Yvette Cedex,

    Averty, X
    Research Engineer, CEA-Saclay, DEN/DMN/SEMI, Gif Sur Yvette Cedex,

    Yvon, P
    Head of Service, CEA-Saclay, DEN/DMN/SEMI, Gif Sur Yvette Cedex,


    Stock #: JAI12465

    ISSN: 1546-962X

    DOI: 10.1520/JAI12465

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    Author
    Title Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior
    Symposium Zirconium in the Nuclear Industry: Fourteenth International Symposium, 2004-06-15
    Committee B10