The aim of this study was to investigate the nuclear fuel evolution and the neutronic parameters of a lead-cooled Accelerator-Driven Systems (ADS) used for fuel breeding and transmutation of spent fuel. The simulated core was a cylinder fueled with a hexagonal lattice with 156 fuel rods. The fuel used was a mixture based upon Pu-MA, removed from PWR-spent fuel, reprocessed by GANEX and spiked with 82% of thorium. Monteburns 2.0 (MCNP5/ORIGEN 2.1) code was used to simulate the neutronic aspects of the fuel. The multiplication factor, neutron spectra and nuclear fuel evolution were analyzed during 10 years of burn-up. The results indicated that the use of GANEX fuel spiked with thorium allowed U-233 production and reduction in the amount of high radiotoxicity isotopes. Copyright (C) 2015, Hydrogen Energy Publications, LLC. Published by Elsevier Ltd. All rights reserved.