Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data

The primary target of this work is to improve the level of validation of Monte Carlo based burnup codes using more complex fuel assembly model. The rationale for such improvement is to give the correct surrounding boundary condition for the experimental sample. The selected codes for the analysis are MCNPX2.7.0 and SERPENT2.1.21 with intrinsic fuel depletion modeling capabilities and VESTA2.14 in conjunction with MCNPX2.7.0 as a neutron transport solver. In particular, emphasis is given to the comparison of the codes, highlighting the performance in term of accuracy of results and computational cost. The same state-of-the-art cross section data library was used to ensure an adequate comparison. Then, fuel assembly model results are also compared with the equivalent pin cell cases results, to highlight the benefits in using more complex models in terms of gain in accuracy compared to experimental values.