Parametrical studies on Pu burning in fast reactors

This paper presents a neutron-physics parametrical study on fast reactor cores considered for plutonium (Pu) burning. The Pu consumption is shown to be a function of the Pu enrichment in the fuel. Different design options are considered that would permit practical us of highly enriched mixed oxide (MOX) fuels. Both sodium void reactivity and Doppler constant are important criteria of selection since they are largely influenced by the design options. Alternatively to MOX fuel, advanced fuel types without uranium for Pu burning enhancement are considered, and their impact on the core performance have been calculated. (authors)