Evaluation of high thermal conductivity oxide nuclear fuel concept containing beryllium
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Beryllium oxide (BeO) is proposed as an engineered additive to enhance the thermal conductivity of UO2. Processing methods to fabricate UO 2-10 vol% BeO have been established and a finite element thermal model has been created to predict the behavior of this fuel Further, two-dimensional, infinite lattice neutronic simulations were performed for a typical PWR system. It was determined that the BOC reactivity may increase by 2800 pcm, resulting in and increase in cycle length of 20 days with a potential increase in EOC burnup of 4000 MWd/tHM. Fuel and moderator reactivity coefficients were estimated to be similar those found with pure UO2 fuel.