Abstract This work is a part of the International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) titled: \Benchmarks of Computational Tools against Experimental Data on Fuel Burnup and Material Activation for Utilization, Operation and Safety Analysis of Research Reactors". The OPAL research reactor has been modelled using MCNP codes as a benchmark study. Neutron flux profiles, critical configurations, control rod worths, fuel burnup and kinetic parameters have been calculated. Comparisons between the calculated results and the experimental data given in the OPAL benchmark have been performed.