Solvent Extraction Flowsheet Studies with Irradiated Fuel from the Fast Flux Test Facility

摘要

A small batch (approx. 2 kg) of irradiated fuel from the Fast Flux Test Facility (FFTF) was recently used as feed for some solvent extraction experiments that were made in the Solvent Extraction Test Facility (SETF). This fuel, which was from series DEA-1, had been irradiated to a burnup of approx. 0.26 TJ/kg (approx. 3000 MWd/t) and cooled for approx. 1 year. The SETF is located in one of the heavily shielded hot cells of the Transuranium Processing Plant at the Oak Ridge National Laboratory. This facility has been used during the past several years to demonstrate the suitability of conceptual flowsheets for the solvent extraction processing of irradiated light-water reactor and fast breeder reactor fuels. Results of these experiments have provided information on uranium and plutonium separation and recoveries, fission product decontamination, comparisons of flowsheet options, and general operability of the system. (ERA citation 09:042933)