Abstract
Closeness of electrochemical properties of uranium and zirconium makes separation of these metals in pyroelectrochemical reprocessing of spent nuclear fuels a challenging task. Varying electrode material can change metals’ deposition potentials. The study was aimed at assessing the effect of the cathode material on deposition potentials of zirconium and uranium from 3LiCl–2KCl based melts. Solid (tungsten) and liquid (gallium, zinc, Ga–Zn, Ga–Sn and Ga–In alloy) working electrodes were tested at 532–637 °C. Galvanostatic cathodic polarization was employed and the applied cathodic current varied from 0.0001 to 1 A. Gallium–zinc eutectic alloy demonstrated the largest difference of zirconium and uranium deposition potentials. Zirconium/uranium separation factors were experimentally determined in a “molten salt—liquid metal” system for gallium and Ga–Zn eutectic based alloys.
Funder
Russian Science Foundation
Subject
General Materials Science,Metals and Alloys
Reference28 articles.
1. The Nuclear Fuel Cycle: From Ore to Wastes;Wilson,1996
2. Electrode Potentials in Fused Chlorides;Smirnov,1973
3. Anodic dissolution of zirconium and hafnium in salt melts;Baraboshkin;Proc. Inst. Electrochem. UBAS USSR,1962
4. Cathodic processes at current densities exceeding the limiting diffusion one;Komarov;Proc. Inst. Electrochem. UBAS USSR,1961
5. Nuclear-grade zirconium prepared by combining combustion synthesis with molten-salt electrorefining technique
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