In recent decades, nuclear power generation industries have been focused on the improvement and development of reactor technology. Different Generation-IV reactors have been proposed to extend the burn-up, improve the passive safety, and have a suitable manage of the radioactive waste and the possibility of using reprocessed fuels containing minor actinides. In this study, the GFR (Gas-cooled Fast Reactor) was evaluated using three different fuel compositions: conventional (U,Pu)C and two reprocessed fuels with transuranic (TRU) (Pu, Am, Np, Cm). One reprocessed by UREX+ technique and spiked with depleted uranium, (U,TRU)C, and the other reprocessed by the same technique but spiked with thorium, (Th,TRU)C. The reprocessed fuel came from a PWR standard fuel (33,000 MWd/T burned) with 3.1% of initial enrichment and left in pool by 5 years. The goal is to validate the simulated model and evaluate the possibility to use TRU spiked with Th in GFR.
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