Abstract: Super Monte Carlo Program for Nuclear and Radiation Simulation (SuperMC), a general, intelligent, accurate and precise simulation software system for the design and safety evaluation of nuclear systems, is developed by FDS team of key laboratory of neutronics and radiation safety. In order to validate the accuracy of SuperMC in calculating MOX-fueled system, it was benchmarked with the VENUS-Ⅱ MOX-fueled core model released by OECD/NEA. Both cell and core calculations were performed. A series of key parameters of cell infinite multiplication factor, reaction rates per heavy isotope, core effective multiplication factor, and axial fission rate distribution of six fuel pins were calculated. The computational results are compared with measured data and the MCNP calculated results, showing that the SuperMC results agree well with the experimental results and the MCNP calculated results. The correctness and reliability of SuperMC calculating neutron transport in MOX-fuelled system are preliminarily verified.