Volume 5, Issue 5 (May 2008)

    A New Model to Predict the Oxidation Kinetics of Zirconium Alloys in a Pressurized Water Reactor

    (Received 19 June 2007; accepted 8 April 2008)

    Published Online: 2008

    CODEN: JAIOAD

      Format Pages Price  
    PDF Version 23 $25   ADD TO CART


    Abstract

    The previous CEA corrosion code COCHISE provided satisfactory simulations of in-reactor corrosion of the fuel cladding when used in its validity range. In contrast, it could lead to hazardous predictions if applied out of this range due to the strongly linked parameters mainly based on the analysis of French pressurized water reactor (PWR) data. To predict the oxidation kinetics for new operating conditions or new materials, the CEA and EDF decided to develop a new model, named CORCY, which is based on a more phenomenological approach and uses separate parameters deduced from analytical experiments. The aim of this paper is to present the new model for Zircaloy-4 in PWR. The phenomenological approach is described. It is based on out- and in-pile data. Typically, since (1) the oxidation kinetics of zirconium alloys in autoclave are periodic, and (2) the oxide films formed in autoclave, in out-of-pile loop, and in-reactor all exhibit periodic lateral cracks with a period similar to the oxide thickness to transition, the oxidation kinetics in CORCY are characterized by a cyclic repetition of semi-parabolic law. Each model parameter is detailed. They are deduced separately from (a) oxidation tests performed in autoclave on fresh alloys to determine their kinetics; (b) oxidation tests performed in the out-of-pile corrosion loops Corail and Reggae to quantify the effects of thermo-hydraulic conditions; (c) data provided by Testing Material Reactors (OSIRIS and Halden reactor) during isothermal oxidation to determine the effects of irradiation; and (d) oxidation tests performed on pre-hydrided alloys to take into account the accelerated corrosion phase occurring, in reactor, for Zircaloy-4 at high burn-up. After describing both the phenomenological approach and the different model parameters, a comparison of measured and calculated corrosion data from French PWRs at a burn-up up to 65 GWd/tU is provided.


    Author Information:

    Bouineau, V.
    CEA/Cadarache,

    Ambard, A.
    EDF R&D MMC site des Renardières,

    Bénier, G.
    CEA/Cadarache,

    Pêcheur, D.
    CEA/Cadarache,

    Godlewski, J.
    CEA-DEN,

    Fayette, L.
    CEA/Cadarache,

    Duverneix, T.
    CEA/Cadarache,


    Stock #: JAI101312

    ISSN: 1546-962X

    DOI: 10.1520/JAI101312

    ASTM International is a member of CrossRef.

    Author
    Title A New Model to Predict the Oxidation Kinetics of Zirconium Alloys in a Pressurized Water Reactor
    Symposium 15th International Symposium on Zirconium in the Nuclear Industry, 2007-06-28
    Committee B10