International Workshop on

    Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors

    OECD Conference Centre, 2 rue André Pascal
    Paris, France
    7-9 March 2017

    Announcement

    Final programme

    Workshop material (for registered participants only) (password protected | reminder)

    Background

    Advanced techniques for fuel modelling have progressed considerably in the last decade in part aided due to progress in high-performance computational capability. At the engineering scale, this has resulted in improved mechanistic description within fuel performance codes with a trend to progressively replace empirical models and correlations with physical models that allow, in principle, extension of the predictive capability of the codes beyond the domain for which experimental results are available. As an example, mesoscale codes (at the fuel-grain scale, typically microns) provide predictions of microstructure evolution and determine their impact on fuel properties, describing phenomena such as grain-boundary sweeping, grain growth, bubble nucleation, growth and coalescence, precipitation of solid fission products, their speciation and phase separation. Inclusion of these models within engineering-oriented fuel performance codes offers improved predictions of thermal conductivity, elastic constants, swelling, and fission-gas release under conditions beyond their usual range of validity and creates an exploratory capability. At the OECD Nuclear Energy Agency, the importance of fuel modelling and its improvement through development of phenomenological representations has been recognized, and multiple technical groups related to materials modelling and the support of advanced fuels and safety codes are considering these issues. A prime example is the Working Party on Multiscale Modelling of Fuels and Structural Materials for Nuclear Energy Systems, and in particular the Expert Group on Multiscale Modelling of Fuels, which published in October 2015 a State-of-the-Art Report on Multi-scale Modelling of Nuclear Fuels. To improve the coordination of these activities and to identify future needs within the NEA and in the broader technical world, a workshop on Nuclear fuel modelling in support of safety and performance enhancement for water-cooled reactors was proposed.

    Objectives and scope

    The main objectives of the workshop were:

    • to identify areas where advanced rod-scale, mesoscale or microscale plus multiscale integration modelling of nuclear fuels was contributing or would contribute to significant progress on or insights into fuel safety and/or fuel performance for water-cooled reactors; the focus was on the design and operation of nuclear fuel, with consideration of nominal and off-nominal operating conditions including design-basis accidents;
    • to identify impacts the advanced modelling approaches might have on the current nuclear fuel design safety limits (evolution or new types of safety limits);
    • to identify gaps in models/information and possible experimental needs;
    • to identify areas for enhanced international collaboration and contribution by the NEA.
    The workshop included keynote presentations, technical talks and panel discussions involving experts from a broad spectrum of stakeholders, including R&D organisations, academia, industry and regulatory bodies within NEA member countries, as well as representatives of others international bodies. The workshop topics included major insights related to performance and safety improvements during normal operation and under off-normal conditions for water-cooled reactors nuclear fuel, including:
    • release of fission gases;
    • formation of high burn-up structures (rim and MOX clusters);
    • fuel swelling (diametral and axial) and PCI;
    • the impact of dopants such as gadolinia;
    • analytical investigation of the margins associated with fuel-safety criteria including uncertainties;
    • other issues such as clad oxidation, CRUD deposition, fretting, fuel assembly bowing;
    • factors affecting burn-up and cycle length, power uprates, and more flexible modes of operation;
    • reduction of uncertainties in the fuel design process and consequences on the licensing margins;
    • fuel fragmentation under LOCA conditions.

    Schedule

    • 15 December 2016: registration opens;
    • 24 February 2017: deadline for registrations;
    • 7 March 2017: workshop opens at 9 am, OECD Conference Centre (Paris).

    Registration

    There was no fee for participation in this workshop.

    General co-chairs

    Kemal Pasamehmetoglu
    INL (USA), Chair of NEA Expert Group on Accident Tolerant Fuels for LWRs

    Marc Petit
    IRSN (France), Chair of NEA Working Group on Fuel Safety

    Ted Besmann
    University of South Carolina (USA), Chair of NEA Working Party on Multiscale Modelling of Fuels and Structural Materials

    Scientific Advisory Committee

    T. Besmann (USC) G. Rossiter (NNL)
    M. Freyss (CEA) D. Tsurikov (Kurchatov Institute)
    V. Garat (AREVA) P. van Uffelen (EC-JRC)
    C.B. Lee (KAERI) C. Valot (CEA)
    S. Middleburgh (Westinghouse) M. Veshchunov (IAEA)
    M. Moatti (EDF) N. Waeckel (EDF)
    F. Nagase (JAEA) W. Wiesenack (IFE-HRP)
    K. Pasamehmetoglu (INL) B. Wirth (UT-ORNL)
    M. Petit (IRSN) K. Yueh (EPRI)