Abstract: A method of processing spent TRIZO-coated nuclear fuel may include adding fluoride to complex zirconium present in a dissolved TRIZO-coated fuel. Complexing the zirconium with fluoride may reduce or eliminate the potential for zirconium to interfere with the extraction of uranium and/or transuranics from fission materials in the spent nuclear fuel.

Abstract: Process for treating spent nuclear fuel (SNF) to make mixed metal oxides of UO3 and PuO2 to prevent nuclear proliferation. The process comprises the steps of (1) dissolving spent nuclear fuel in an acidic solution in the presence of an agent that reduces Pu+6 to Pu+4 and an agent that oxidizes Pu+3 to Pu+4; (2) extracting U+6 and Pu+4 from acidic solution with an organic solvent comprising a ligand that binds U+6 and Pu+4 and which is soluble in the organic solvent; (3) jointly extracting U+6 and Pu+4 from the organic solvent with an acidic aqueous solution; and (4) precipitating a mixture of U+6 and Pu+4 by adding a carboxylic acid to the acidic aqueous solution. The U+6 and Pu+4 precipitate is then be calcined to form a mixed metal oxide of UO3 and PuO2. Additional steps can result in the formation of a mixed metal oxide of UO3, PuO2 and NpO2 as well as the removal and isolation of technecium from the SNF.

Abstract: Process for treating compositions containing uranium and plutonium, including spent nuclear fuel, are provided.