Neutronic Analysis of TRISO Coated Candu Spent Fuel in A Hybrid Reactor

In this study, time dependent performance of incineration of the triso fuel containing candu spent fuels in the deuterium-tritium (d-t) fusion driven hybrid reactor was investigated. neutron transport calculations were performed by using xsdrnpm/scale 5 codes. in the reactor model, neutral lithium, flibe, flinabe and li20sn80 were used as coolants. in the calculations, the effect of triso fuel containing candu spent fuels on tritium breeding ratio (tbr), energy multiplication (m), fissile fuel breeding (ffb) and average burn up values were comparatively investigated. according to the time dependent calculations, it was observed that triso fuel containing candu spent fuels extends the burn-up.