Spent nuclear fuel (SNF) from modern light water or thermal reactors containing uranium
oxide with small concentrations of plutonium and other actinide oxides is converted into …

Extensive research and process development has been conducted on the electrolytic
reduction of actinide oxides in molten LiCl-Li 2 O. It is now accepted that the reduction of …

This paper reports the direct separation of U from lanthanides (Ln) in oxide mixtures in LiCl-
KCl eutectic, a method that could simplify the pyrometallurgical reprocessing of UO 2-based …

This work presents the electrochemical behavior of U 3 O 8 and the formation of Al-U
intermetallics in LiCl-KCl-AlCl 3 melts at 813 K by various electrochemical test methods. The …

To extract dysprosium (Dy) from LiCl–KCl molten salt, the electrochemical properties of Dy
on liquid Sn electrode were explored by various electrochemical methods such as cyclic …

The reduction of pellets composed of individual CeO2, Nd2O3 and a La2O3-Nd2O3-CeO2
mixture by lithium extracted on a cathode during lithium chloride electrolysis at 650° C was …

Abstract Uranium-molybdenum (U-Mo) alloys especially the γ-U-Mo phase, with excellent
irradiation performance at high temperatures, have been extensively studied as low …

Reduction of ZrO 2 by lithium during electrolysis of LiCl-KCl-Li 2 O melt at 650 C was studied
using a set of physicochemical methods of analysis. Influence of ZrO 2 in the space near a …

A common kinetic feature for oxide reduction chemical/electrochemical processes is oxygen
transport via a porous metallic layer, which has been considered as a rate-determining step …

For UO 2-based spent fuel, it is usually electrochemically reduced and then refined in molten
salt with respect to the so-called pyrochemical reprocessing approach. In this work, we …