Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Voltammetry measurements in lithium chloride-lithium oxide (LiCl–Li2O) salt: An evaluation of working electrode materials

Journal Article · · Journal of Nuclear Materials
Instrumentation to provide process monitoring (PM) and safeguards for the oxide reduction (OR) step in the electrochemical processing of used oxide nuclear fuel is necessary to ensure equipment is operated as declared. Cyclic voltammetry (CV) has been proposed for real-time monitoring of the operation of an OR process for safeguards purposes. In this study, different materials including 316 stainless steel (SS), tantalum (Ta), molybdenum (Mo), tungsten (W), platinum (Pt), and iridium (Ir) were evaluated as potential working electrode (WE) materials based on their chemical inertness, corrosion resistance, and sensitivity in detecting Li2O and other chloride salts in the OR electrolyte. Of the electrodes evaluated, 316 SS, Ir, and Pt all performed reasonably well in the LiCl-Li2O electrolyte. Here, stainless steel was operated in the cathodic potential and had reasonable corrosion resistance and is relatively inexpensive. Iridium could be operated in both the cathodic and anodic potentials and was the most corrosion resistant of those evaluated. Platinum is limited to the anodic potential range, had reasonable corrosion resistance, and was the most sensitive to Li2O concentrations in the salt. In the development of a stand-alone safeguards instrumentation, our recommendation is a CV sensor fitted with both Ir and Pt WEs. The results in this study may also be helpful for anode material selection in other electrometallurgy industries, such as molten salt electrolysis.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE; USDOE Office of Environment, Health, Safety and Security (AU), Office of Security; USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1768062
Alternate ID(s):
OSTI ID: 1776050
Report Number(s):
INL/JOU--20-58959-Rev000
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 546; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (25)

Comparative study of monolithic platinum and iridium as oxygen-evolving anodes during the electrolytic reduction of uranium oxide in a molten LiCl–Li2O electrolyte journal February 2019
Preparation of uranium(III) in a molten chloride salt: a redox mechanistic study journal June 2018
Determination of kinetic properties of Sm(III)/Sm(II) reaction in LiCl–KCl molten salt using cyclic voltammetry and electrochemical impedance spectroscopy journal September 2019
Oxide electroreduction and other processes for pyrochemical processing of spent nuclear fuels book January 2015
Development of closed nuclear fuel cycles in Korea book January 2015
Electrolytic reduction behavior of U3O8 in a molten LiCl–Li2O salt journal July 2008
Underpotential deposition of Li in a molten LiCl–Li2O electrolyte for the electrochemical reduction of U from uranium oxides journal May 2010
Aluminum assisted electrodeposition of europium in LiCl–KCl molten salt journal March 2010
A cyclic voltammetry study of the electrochemical behavior of platinum in oxide-ion rich LiCl melts journal September 2014
Electrochemical behaviors of Dy(III) and its co-reduction with Al(III) in molten LiCl-KCl salts journal November 2014
Applicability of nickel ferrite anode to electrolytic reduction of metal oxides in LiCl-Li 2 O melt at 923 K journal January 2016
Study on the exchange current density of lanthanide chlorides in LiCl-KCl molten salt journal February 2019
Electrochemical studies and analysis of 1–10wt% UCl3 concentrations in molten LiCl–KCl eutectic journal September 2014
Measurement of europium (III)/europium (II) couple in fluoride molten salt for redox control in a molten salt reactor concept journal December 2017
Identification, measurement, and mitigation of key impurities in LiCl-Li2O used for direct electrolytic reduction of UO2 journal November 2018
Electrochemical processing of spent nuclear fuels: An overview of oxide reduction in pyroprocessing technology journal December 2015
Electrochemistry of the Hall-Heroult process for aluminum smelting journal April 1983
Direct electrochemical reduction of titanium dioxide to titanium in molten calcium chloride journal September 2000
Redox Equilibrium of U 4+ /U 3+ in Molten NaCL-2CsCL by UV-Vis Spectrophotometry and Cyclic Voltammetry journal December 2005
Kinetic Parameters and Diffusivity of Uranium in FLiNaK and ClLiK journal July 2020
Electrochemical Properties and Analyses of CeCl 3 in LiCl-KCl Eutectic Salt journal January 2015
A Study of Graphite as Anode in the Electro-Deoxidation of Solid UO 2 in LiCl-Li 2 O Melt journal January 2015
The FFC Cambridge process and its relevance to valorisation of ilmenite and titanium-rich slag journal November 2014
Separation and Recovery of Uranium Metal from Spent Light Water Reactor Fuel Via Electrolytic Reduction and Electrorefining journal September 2010
Electrochemical Impedance Spectroscopy and Cyclic Voltammetry Methods for Monitoring SmCl3 Concentration in Molten Eutectic LiCl-KCl journal March 2020