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

Autor: S.A Slater, A.G Raraz, J.L Willit, E.C Gay
Rok vydání: 1999
Předmět:
Zdroj: Separation and Purification Technology. 15:197-205
ISSN: 1383-5866
DOI: 10.1016/s1383-5866(98)00101-4
Popis: 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.
Databáze: OpenAIRE