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Electrochemical separation of aluminum from uranium for research reactor spent nuclear fuel applications.

Journal Article · · Sep. Purif. Technol.
Researchers at Argonne National Laboratory (ANL) are developing an electrorefining process to treat aluminum-based spent nuclear fuel by electrochemically separating aluminum from uranium. The aluminum electrorefiner is modeled after the high-throughput electrorefiner developed at ANL. Aluminum is electrorefined, using a fluoride salt electrolyte, in a potential range of -0.1 V to -0.2 V, while uranium is electrorefined in a potential range of -0.3 V to -0.4 V; therefore, aluminum can be selectively separated electrochemically from uranium. A series of laboratory-scale experiments was performed to demonstrate the aluminum electrorefining concept. These experiments involved selecting an electrolyte (determining a suitable fluoride salt composition); selecting a crucible material for the electrochemical cell; optimizing the operating conditions; determining the effect of adding alkaline and rare earth elements to the electrolyte; and demonstrating the electrochemical separation of aluminum from uranium, using a U-Al-Si alloy as a simulant for aluminum-based spent nuclear fuel. Results of the laboratory-scale experiments indicate that aluminum can be selectively electrotransported from the anode to the cathode, while uranium remains in the anode basket.
Research Organization:
Argonne National Laboratory (ANL)
DOE Contract Number:
AC02-06CH11357
OSTI ID:
938332
Report Number(s):
ANL/CMT/JA-29406
Journal Information:
Sep. Purif. Technol., Journal Name: Sep. Purif. Technol. Journal Issue: 1999 Vol. 15; ISSN 1383-5866; ISSN SPUTFP
Country of Publication:
United States
Language:
ENGLISH