Simulation of Irradiation Effects in Reactor Pressure Vessel Steels: the Reactor for Virtual Experiments (REVE) Project

    Volume 30, Issue 1 (January 2002)

    ISSN: 0090-3973

    CODEN: JTEOAD

    Page Count: 10


    Jumel, S
    R & D Division of Electricity of France (EDF) - Les Renandières, Moret sur Loing,

    Laboratoire de Métallurgie Physique et Génie des Matériaux - UMR 1577, Université de Lille, Villeneuve d'Ascq,

    Domain, C
    R & D Division of Electricity of France (EDF) - Les Renandières, Moret sur Loing,

    Laboratoire de Métallurgie Physique et Génie des Matériaux - UMR 1577, Université de Lille, Villeneuve d'Ascq,

    Ruste, J
    R & D Division of Electricity of France (EDF) - Les Renandières, Moret sur Loing,

    Van Duysen, J-C
    R & D Division of Electricity of France (EDF) - Les Renandières, Moret sur Loing,

    Laboratoire de Métallurgie Physique et Génie des Matériaux - UMR 1577, Université de Lille, Villeneuve d'Ascq,

    Becquart, C
    Laboratoire de Métallurgie Physique et Génie des Matériaux - UMR 1577, Université de Lille, Villeneuve d'Ascq,

    Legris, A
    Laboratoire de Métallurgie Physique et Génie des Matériaux - UMR 1577, Université de Lille, Villeneuve d'Ascq,

    Pareige, P
    Groupe de Physique des Matériaux - UMR 6634, Université de Ronen, Mont saint Aignan,

    Barbu, A
    Ecole Polytechnique - SESI/CEA-CEREM, Gif-sur Yvette,

    Van Walle, E
    Centre d'Etude de l'Energie Nucléaire, Mol,

    Chaouadi, R
    Centre d'Etude de l'Energie Nucléaire, Mol,

    Hou, M
    Laboratoire de Physique et des Soldes Irradiés, Université Libre de Bruxelles,

    Odette, GR
    University of California, Santa Barbara, CA

    Stoller, RE
    Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, TN

    Wirth, BD
    Materials Division of Lawrence Livermore National Laboratory, Livermore, CA

    (Received 17 January 2001; accepted 6 August 2001)

    Abstract

    Components of commercial nuclear reactors are subjected to neutron bombardments that can modify their mechanical properties. Prediction of in-service and post-service behaviors generally requires irradiation in so-called “test reactors” as well as subsequent mechanical testing in specialized hot cell facilities. However, the use of these research facilities is becoming more problematic, in particular due to increasing costs and decreasing availability. One way of partially mitigating these problems is to complement the empirical approach by developing tools for numerical simulation of irradiation effects in materials. The development of such tools is clearly an ambitious task that will require a long-term international collaborative effort.

    In this paper, we present an outline of the Reactor for Virtual Experiments (REVE) project, a collaborative European and American effort aimed at developing quantitative simulations of irradiation effects in materials. The first demonstration phase of REVE will target embrittlement of reactor pressure vessel (RPV) steels, since the effects and mechanisms of irradiation damage in this material are relatively well understood and many modeling tools have been developed or are under development in this field. As for any experiment, the input variables of the REVE simulation will be the neutron spectrum, time and temperature of irradiation, the alloy composition (e.g., Cu, Ni, Mn, and C contents) and microstructure and the unirradiated mechanical properties. The simulations will predict the irradiation-induced increases of yield stress and Charpy transition temperature as well as the decrease of toughness due to the concomitant evolution of the microstructure.


    Paper ID: JTE12287J

    DOI: 10.1520/JTE12287J

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    Author
    Title Simulation of Irradiation Effects in Reactor Pressure Vessel Steels: the Reactor for Virtual Experiments (REVE) Project
    Symposium , 0000-00-00
    Committee E10