A “Two-Step” Electrochemical Approach for Recovery of Plutonium and Uranium from Aqueous Acidic Waste Solutions

Abstract

Chemical quality control of nuclear fuel, particularly the determination of Pu and U contents by chemical methods, results in analytical acidic aqueous waste solutions from which Pu and U must be recovered efficiently for the remediation of radioactive wastes. Reported methods involve several complicated steps requiring addition of chemical oxidants/reductants for valence adjustments and generation of secondary wastes, thereby making the recovery process cumbersome. Herein, we report a novel two-step electrochemical approach for Pu and U recovery from acidic aqueous waste solutions containing different metallic impurities (Fe, Cr, Mn, Cd, Al, Ni, Co, Zn, and Mg) by bulk electrolysis using a Pt gauze electrode. Pu and U are recovered from these waste solutions in a two-step process: (i) bulk electrolysis of the mixed solution at a constant potential of 0.1 V vs Ag/AgCl/3 M KCl that results in the reduction of PuO 2 2+ to Pu 3+ followed by the precipitation of Pu 3+ as K 2 (K 0.5 Pu 0.5 )(SO 4 ) 2 , which is then filtered and separated and (ii) the filtrate solution is again subjected to bulk electrolysis at a constant potential of −0.35 V vs Ag/AgCl/3 M KCl resulting in the reduction of UO 2 2+ to U 4+ . The U 4+ is then precipitated as K 2 (K 0.67 U 0.33 )(SO 4 ) 2 , which is filtered and separated, leading to a Pu-and U-free aqueous acidic waste solutions. Biamperometry shows that 97.8% and 99.1% recovery of Pu and U, respectively, is possible, and emission spectrometry confirms the purity of K 2 (K 0.5 Pu 0.5 )(SO 4 ) 2 and K 2 (K 0.67 U 0.33 )(SO 4 ) 2 . Because of its operational simplicity, potential for remote handling, and excellent extraction efficiency, the present methodology can easily replace traditional methods for the recovery of Pu and U from acidic aqueous waste solutions.

Actinide Sulfate Structures from Caustic Solvents

“…The sulfate oxyanion is important in the nuclear fuel cycle due to various uses throughout. Sulfuric acid is a main constituent in in situ leaching of uranium to mine uranium ore for nuclear fuel. , Additionally, plutonium­(III) sulfate has been found to be a main precipitant in newer separations using electrolysis to recover plutonium from used nuclear fuel …”