CX-017192: Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear Fuel

Categorical Exclusion Determination

Office of NEPA Policy and Compliance

October 30, 2017
Estimated Read Time   min

The purpose of the proposed action is to study the exchange chemistry between irradiated mixed-oxide fuel from the Fast Flux Test Reactor and a ternary molten salt, e.g. sodium chloride-potassium chloride-zirconium (IV) chloride. The zirconium (IV) chloride is expected to convert the actinide oxides and many of the fission product oxides in the mixed oxide fuel into metal chlorides in the molten salt.