Three-dimensional neutronic calculations for a fusion breeder APEX reactor using some libraries

► We calculated effects of evaluated nuclear data files on neutronics characteristics. ► We used the MCNP4C Monte Carlo code for three-dimensional calculations. ► TBR and M values were found greater than 1.1 and 1.2, respectively. ► Fissile fuel breeding was found greatest for ENDF/B-VII library with 4230 kg/year. ► Heat deposition rate values were found approximately the same.