Method for reprocessing and separating spent nuclear fuels. [Patent application]

Patent · Tue Jan 19 04:00:00 EST 1982

OSTI ID:6749349

Krikorian, O H; Grens, J Z; Parrish, Sr, W H

Spent nuclear fuels, including actinide fuels, volatile and nonvolatile fission products, are reprocessed and separated in a molten metal solvent housed in a separation vessel made of a carbon-containing material. A first catalyst, which promotes the solubility and permeability of carbon in the metal solvent, is included. By increasing the solubility and permeability of the carbon in the solvent, the rate at which actinide oxides are reduced (carbothermic reduction) is greatly increased. A second catalyst, included to increase the affinity for nitrogen in the metal solvent, is added to increase the rate at which actinide nitrides form after carbothermic reduction is complete.

• DOE Contract Number: W-7405-ENG-48
• Assignee: Dept. of Energy
• Patent Number(s): None
• Application Number: ON: DE83002352
• OSTI ID: 6749349
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
CARBON
CATALYSTS
CHALCOGENIDES
CHEMICAL REACTIONS
ELEMENTS
ENERGY SOURCES
FLUIDS
FUELS
LIQUID METALS
LIQUIDS
MATERIALS
METALS
NITRIDES
NITROGEN
NITROGEN COMPOUNDS
NONMETALS
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
PNICTIDES
PYROCHEMICAL REPROCESSING
REACTOR MATERIALS
REDUCTION
REPROCESSING
SEPARATION PROCESSES
SPENT FUELS
TIN