Neutronic analysis of Sodium-cooled Fast Reactor (SFR) core with 1000 MWth power and Mix-Oxide (MOX) fuel based on the “Benchmark for Neutronic Analysis of Sodium-cooled Fast Reactor Cores with Various Fuel Types and Core Sizes” has been determine. This study uses a variety of fuels (U,TRU)O2 and (Th,TRU)O2. Calculations were performed using OpenMC with nuclear data ENDF/B-VII.1 for validat…