Feasibility of the electrochemical way in molten fluorides for separating Thorium and Lanthanides and extracting Lanthanides from the solvent.

Pierre Chamelot (1) , Laurent Massot (1) , Céline Hamel (1) , Christophe Nourry , Pierre Taxil

1 LGC - Laboratoire de Génie Chimique

An alternative way of reprocessing nuclear fuel by hydrometallurgy could be using treatment with molten salts, particularly fluoride melts. Moreover, one of the six concepts chosen for GEN IV nuclear reactors (Technology Roadmap – http://gif.inel.gov/roadmap/) is the Molten Salt Reactor (MSR). The originality of the concept is the use of molten salts as liquid fuel and coolant. During the running of the reactor, fission products, particularly lanthanides, accumulate in the melt and have to be eliminated to optimise reactor operation. This study concerns the feasibility of the separation actinides-lanthanides-solvent by selectively electrodepositing the elements to be separated on an inert (Mo, Ta) or a reactive (Ni) cathodic substrate in molten fluoride media. The main results of this work lead to the conclusions that: * The solvents to be used for efficient separation must be fluoride media containing lithium as cation. * Inert substrates are suitable for actinide/lanthanide separation; nickel substrate is more suitable for the extraction of lanthanides from the solvent, owing to the depolarisation occurring in the cathodic process through alloy formation.

Mots clés: Molten fluorides; Lanthanides; Actinides; Electrochemical separation; Alloy formation.

Domaines: Génie chimique

Pierre Chamelot, Laurent Massot, Céline Hamel, Christophe Nourry, Pierre Taxil. Feasibility of the electrochemical way in molten fluorides for separating Thorium and Lanthanides and extracting Lanthanides from the solvent.. Journal of Nuclear Materials, 2007, 360 (1), pp.64-74. ⟨10.1016/j.jnucmat.2006.08.015⟩. ⟨hal-03594321⟩