Investigation of the IAEA benchmark problem using MCNP code

The "IAEA PWR benchmark problem" was intended to draw some conclusions about the accuracy of the different neutronic calculation codes used in the routine deterministic reactor calculation.The objective of this paper is to compare the results obtained using the MCNP computer code with previously obtained results, aiming to provide new reference solutions to the IAEA benchmark using the Monte Carlo method.The effective multiplication factor, the radial and axial assembly power distributions and the zone average group flux were calculated using Monte Carlo code (MCNP) version MCNPX 2.7.0.The MCNP results are compared with the results of deterministic calculations in two and three dimensions.Good estimates of effective multiplication factor and power distribution values were obtained.To assess the MCNP results, the collective percent error measures were determined and values calculated were less than 1%.The results presented in the present study could be considered an accurate solution for the considered IAEA PWR benchmark problem and can be used as Monte Carlo method based reference for this problem.