Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment

The design phase and safety assessment of Generation IV liquid metal-cooled fast reactors calls for the improvement fuel pin performance codes, in particular enhancement their predictive capabilities towards uranium-plutonium mixed oxide fuels stainless-steel cladding under irradiation reactor environments. To this end, current codes must be critically assessed against experimental data from available experiments. This work is devoted to three European namely GERMINAL, MACROS TRANSURANUS, two pins selected SUPERFACT-1 campaign. are characterized by a low enrichment (~ 2 wt.%) minor actinides (neptunium americium) fuel, plutonium content material line with choices envisaged fuels. predictions compared several measurements, allowing identification code predicting restructuring, deformation, redistribution volatile fission products. integral complemented code-to-code benchmark focused on evolution quantities engineering interest over time. analysis points out differences central temperature, fuel-cladding gap width, outer radius, internal pressure gas release suggests potential modelling development paths an improved description behaviour conditions.