When a reactor core contains a large number of multiple cycles and higher burnup plutonium fuel, the core neutronics characteristics will change. To verify the accuracy of current database and existing nuclear software, OECD / NEA proposed VENUS-2 benchmark experiments. Cos MC is designed to perform the Monte Carlo reactor calculation that can handle the complex geometry. In this paper, the latest database and Cos MC is adopted to calculate VENUS-2 benchmark, and the results were compared with other software. The results show that: the calculation results of Cos MC agree well with the experimental results and the measured values. It is demonstrated that it is feasible for Cos MC to calculate the critical problem of the reactor core containing MOX fuel.