“…The objective has been to define bias factors and associated uncertainties (to be used to define design/operation margins) for most design integral parameters. The ANL suite of fast reactor neutronics analysis codes has extensively validated against critical experiments [1][2][3][4][5] and high fidelity Monte Carlo solution [6]. The overall neutronics methodologies including depletion calculations have also been validated using a large experimental database derived from destruction measurements of EBR-II experimental test assemblies and processing irradiated EBR-II fuel assemblies in the Fuel Conditioning Facility [7,8].…”