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

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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
Publication statusPublished - Sep 2008
Event2008 - ICAPP - International Congress on Advances in Nuclear Power Plants - Anaheim, California, United States
Duration: 8 Jun 200812 Jun 2008


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


  • fuel, MOX, modelling, GEN-IV systems

ID: 83880