In order to enrich the calculation methods of physical neutron transport in nuclear reactors in China

the open sources Monte Carlo program OpenMC is validated. Based on ENDF/B-VII.1 database

the whole core modeling and calculation of BEAVRS（Benchmark Evaluation and Validation Reaction Simulations） pressurized water reactor（PWR） were studied by using open sources Monte Carlo program OpenMC to verify the accuracy of the OpenMC program. The results show that the maximum error of the critical eigenvalues calculated by OpenMC program under five critical states is 127 pcm.The calculation errors of control rod value are between-95 and 41 pcm. The maximum relative error of u-235 relative fission rate calculation is-13.6% for B13 assembly. At the same time

the calculated results of OpenMC program are compared with the measured data and the simulation results of similar software. The results show that the calculated results of OpenMC program agree well with the actual situation and are basically better than those of similar software. Therefore

OpenMC program has high accuracy and reliability

and can be widely used in PWR nuclear power plant core simulation calculation.