Validation of Serpent-SCF-TU full-core pin-by-pin burnup calculations using Pre-Konvoi PWR experimental data

The focus of this work is the validation of Serpent-SCF-TU, a high-fidelity multiphysics tool combining Monte Carlo neutron transport, subchannel thermalhydraulics and fuel-performance analysis. A full-core pin-by-pin depletion calculation for the first operating cycle of a Pre-Konvoi PWR plant is presented and the results are assessed using experimental data. The critical boron concentration and a set of pin-level neutron flux profiles are compared against measurements, with very good agreement. The impact of using fuel performance analysis is discussed as well, comparing the three-code coupling with the traditional neutronic-thermalhydraulic approach. The studies presented here are part of the final stage of the EU Horizon 2020 McSAFE project, closing the development cycle of the Serpent-SCF-TU system, from implementation to validation.