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Meeting 2017 TMS Annual Meeting & Exhibition
Symposium High Temperature Electrochemistry III
Presentation Title Initial Operation of Kg-Scale Electrolytic Reduction and Salt Distillation Equipment for the Pyroprocessing of Uranium Oxide in a Hot Cell
Author(s) Steven Herrmann
On-Site Speaker (Planned) Steven Herrmann
Abstract Scope New equipment was designed, fabricated, installed, and operated in the Hot Fuel Examination Facility – an argon atmosphere hot cell at Idaho National Laboratory’s Materials and Fuels Complex – to effect the electrolytic reduction of, and subsequent salt removal from, nuclear oxide fuels at kg-scale. The primary equipment includes an oxide reduction system and an oxide reduction salt distillation apparatus. The oxide reduction system operates with a molten salt pool of LiCl – 1 wt% Li2O at 650 C. Declad and crushed nuclear oxide fuel is loaded into a permeable steel basket and immersed in the oxide reduction salt pool. The basket is connected to power supplies as a common cathode to two separate inert anodes that are also immersed in the oxide reduction salt pool and positioned adjacent to the cathode basket. The power supplies are controlled to electrolytically reduce nuclear oxide fuel to metal in the cathode basket, liberating its oxygen ions to the molten salt where they are simultaneously oxidized to oxygen gas and discharged from the cell at the anode assemblies. The reduced nuclear fuel in the basket is removed from the oxide reduction system and placed in a salt distillation apparatus, where the salt-encrusted fuel and basket are subjected to elevated temperature and reduced pressure to separate the salt from the fuel basket. The salt is collected and returned to the oxide reduction system. The reduced fuel, devoid of oxide reduction salt, is then amenable to further pyroprocessing, as needed. A series of electrolytic reduction and salt distillation operations were performed with unirradiated uranium oxide (UO2) particulate to qualify the prescribed hot cell equipment prior to commencing operations with irradiated materials. Observations from the initial operation of the oxide reduction and salt distillation systems with unirradiated UO2 will be presented in detail.
Proceedings Inclusion? Planned: Supplemental Proceedings volume

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Effects of Oxide Precursor Preparation Parameters on the Electrochemical Reduction of Tantalum Pentoxide in Calcium Chloride Melt
Electrochemical and Thermodynamic Properties of Gadolinium Chloride in LiCl-KCl Eutectic Salt
Electrochemical Behavior of Sn/SnCl2 Cathode in Na | NaCl-AlCl3-SnCl2 | Sn Cell
Electrochemical Deposition of Barium into Liquid Bismuth from BaCl2-LiCl-CaCl2-NaCl Electrolyte
Electrochemical Synthesis of TaC in Molten Salt
Electrochemical Techniques for Nuclear Safeguards in Molten Salt
Electrochemistry in Molten 2LiF-BeF2 Salt for the Fluoride Salt-Cooled High Temperature Reactor Applications
Impurity Removal from Titanium Oxycarbide
Initial Operation of Kg-Scale Electrolytic Reduction and Salt Distillation Equipment for the Pyroprocessing of Uranium Oxide in a Hot Cell
Molten Flux Design for Solid Oxide Membrane Based Electrolysis of Si from Silica
Optimized Voltammetry Methods for Measuring Concentration of Multiple Rare Earths and Actinides in Molten LiCl-KCl
Thermal Imaging Furnace Technique for Ultra-high Temperature Electrochemical Measurements
Thermochemical Properties of Barium-Bismuth Alloys Determined by Emf Measurements
Thorium and Uranium Electrodeposition from Molten LiCl-KCl onto Alpha Spectroscopy Semiconductor Detector Surface
Zirconium Management in the Mk-IV Electrorefiner

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