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Monte Carlo analysis of LWR spent fuel transmutation in a fusionfission hybrid reactor system

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The aim of this paper is to determine neutronic performances of the light water reactor (LWR) spent fuel mixed with fertile thorium fuel in a FFHR. Time dependent three dimensional calculations for major technical data, such as blanket energy multiplication, tritium breeding ratio, cumulative fissile fuel enrichment and burnup have been performed by using Monte Carlo Neutron-Particle Transport code MCNP5 1.4, coupled with a novel interface code MCNPAS. | Monte Carlo analysis of LWR spent fuel transmutation in a fusionfission hybrid reactor system

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