2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference, ICONE 2012-POWER 2012, pp.761 - 766
Abstract
The fuel rod performance of enhanced thermal conductivity UO 2/graphene composites is investigated through a LBLOCA analysis. The benefits increased monotonically with increasing thermal conductivity in terms of reduced fuel center temperature and PCT. The performance of the UO 2/graphene composite fuel is assessed in OPR-1000 (Optimized Power Reactor-1000) during a LBLOCA. Graphene can be a promising material for developing advanced nuclear fuel because of its property about the high thermal conductivity and low absorption cross section. The results confirm a LBLOCA performance related to PCT of the UO2/graphene composite fuel and its potential while maintaining large safety margins.
Publisher
2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference, ICONE 2012-POWER 2012