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Title: Pyroprocessing of Fast Flux Test Facility Nuclear Fuel

Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electrorefined uranium products exceeded 99%.
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Conference: Global 2013: International Nuclear Fuel Cycle,Salt Lake City, UT,09/29/2013,10/03/2013
Research Org:
Idaho National Laboratory (INL)
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Country of Publication:
United States
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS electrochemical; electrometallurgical; pyroprocessing