Safety Parameters Uncertainty and Sensitivity Analysis for High Flux Reactor at Institut Laue Langevin

This study focuses on exploiting the new capabilities (GPT) of Monte Carlo codes to calculate kinetics parameters and their sensitivity to nuclear and experimental data (geometry specifications, material compositions and positions). The results show that GPT is a competitive tool to assess both experimental and nuclear data uncertainties. For the High Flux Reactor (RHF) in particular, the reactivity associated to the flooding of a neutron beam tube is an important safety parameter and a tailored sensitivity analysis is performed.