Development of trail, a simulation code for the molten salt electrorefining of spent nuclear fuel

Abstract

A simulation code for the molten salt electrorefining of spent metallic nuclear fuel from the Integral Fast Reactor has been developed. This code (named trail) employs diffusion layer theory in the vicinity of the electrodes. Model parameters such as the diffusion layer thickness were determined from polarization data measured with uranium at different concentrations in the molten salt electrolyte and liquid cadmium anode of an electrorefining cell. Calculations were made to verify the code with experimental data for various operational modes. Good agreement with the data was obtained. It was also found that this code can provide useful information to aid in understanding the electrotransport process within the electrorefiner.