Reprocessing of spent nuclear fuel comprises extracting uranium and plutonium with nitric acid in selected organic solvents

摘要

Reprocessing of spent nuclear fuel comprises extracting uranium and plutonium with nitric acid in an amide, methyl isobutyl ketone, diethylene glycol dibutyl ether or beta-diketone solvent, reextracting plutonium from the extract with nitric acid containing a reducing agent, denitrating the plutonium solution to recover plutonium oxide, reextracting uranium from the extract with nitric acid and denitrating the uranium solution to recover uranium oxide. Independent claims are also included for: (1) reprocessing of spent nuclear fuel by extracting uranium and plutonium with nitric acid in an amide, methyl isobutyl ketone or diethylene glycol dibutyl ether solvent, reextracting plutonium from the extract with nitric acid containing a reducing agent, denitrating the plutonium solution to recover plutonium oxide, and burning the extract to recover uranium oxide; (2) reprocessing of spent nuclear fuel by extracting uranium and plutonium with nitric acid in a methyl isobutyl ketone or beta-diketone solvent, reextracting plutonium from the extract with nitric acid containing a reducing agent, denitrating the plutonium solution to recover plutonium oxide, distilling the extract to remove the solvent and denitrating the residual uranium nitrate to recover uranium oxide.