Abstract: The critical calculation capacity of RMC (Reactor Monte Carlo Code) was verified based on the core power distribution verification benchmark released by OECD/NEA. The data of ENDF/B-Ⅵ library were used by RMC, and the whole core eigenvalues were calculated and the 1/8 pin-by-pin fission rate was counted. Comparisons were made among the benchmark eigenvalues and those outputs by the RMC code and MCNP. The eigenvalue calculation results are in good agreement with the reference and the outputs of MCNP. The fission rate calculated by this work has an average relative deviation of 2.89% compared with the reference, and 0.5% with MCNP. The fission rate and absorption rate of different nuclides were calculated as well as the eigenvalues of four different cells. The results agree well with the reference data, which indicates that RMC has a good performance in core critical calculation capacity and the results provide a direct reference for the similar problem calculation.