Preliminary analysis by means of the TRANSURANUS code of mixed oxide fuel rod for Gen IV lead fast reactor

F. Vettraino, R. Calabrese, C. Artioli, L. Luzzi, Vitaly Sobolev, Marc Verwerft

    Research outputpeer-review


    In this paper, a TRANSURANUS fuel rod thermo-mechanical analysis is performed under the European Lead-cooled SYstem (ELSY project– FP6 ) conditions. The ELSY project is a 600 MWe reactor MOX-fuelled (nitride fuel as future option). Lead assures a prominent coolant chemical inertness and favourable neutronic properties under fast neutron spectrum. In ELSY main GEN IV goals are pursued (sustainability, economics, safety and reliability, proliferation resistance and physical protection). This preliminary ELSY fuel pin analysis aims at investigating by deterministic and statistical methods possible deviations of fuel rod performance moving from reference MOX to a Minor Actinides (MAs) bearing mixed oxide fuel (closed fuel cycle option).
    Original languageEnglish
    Title of host publicationInternational Congress on Advances in Nuclear Power Plants, ICAPP 2008
    Place of PublicationNew York, United States
    StatePublished - Sep 2008
    Event2008 - ICAPP - International Congress on Advances in Nuclear Power Plants - Anaheim, California
    Duration: 8 Jun 200812 Jun 2008


    Conference2008 - ICAPP - International Congress on Advances in Nuclear Power Plants
    Country/TerritoryUnited States
    CityAnaheim, California
    Internet address

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