Preliminary analysis by means of the TRANSURANUS code of mixed oxide fuel rod for Gen IV lead fast reactor
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Abstract
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).
Details
| Original language | English |
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| Title of host publication | International Congress on Advances in Nuclear Power Plants, ICAPP 2008 |
| Place of Publication | New York, United States |
| Publication status | Published - Sep 2008 |
| Event | 2008 - ICAPP - International Congress on Advances in Nuclear Power Plants - Anaheim, California, United States Duration: 8 Jun 2008 → 12 Jun 2008 http://www.inspi.ufl.edu/icapp08/ |
Conference
| Conference | 2008 - ICAPP - International Congress on Advances in Nuclear Power Plants |
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| Country/Territory | United States |
| City | Anaheim, California |
| Period | 2008-06-08 → 2008-06-12 |
| Internet address |
Keywords
- fuel, MOX, modelling, GEN-IV systems
ID: 83880