A pyrochemical processing has become one of the potential technologies for a future nuclear fuel cycle. An integrated multi-physics
simulation and electrotransport model of a molten-salt electrolytic process are proposed and discussed with respect to the
recovery of pure uranium when using thermochemical data. This study has been performed to provide information for diffusion
boundary layers between the molten salt (KCl-LiCl) and electrode. The diffusion-controlled electrochemical model demonstrate
a prediction of the electrotransport behaviors of LWR spent fuel as a function of the time up to the corresponding electrotransport
satisfying a given applied current based on a galvanostatic electrolysis.