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.