Method for reprocessing and separating spent nuclear fuels

Patent · Tue Aug 16 04:00:00 EDT 1983

OSTI ID:5647259

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

Spent nuclear fuels, including actinide fuels, volatile and non-volatile 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.

• Assignee: EDB-84-013190
• Patent Number(s): US 4399108
• OSTI ID: 5647259
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
CARBON
CATALYSTS
COBALT
ELEMENTAL MINERALS
ELEMENTS
ENERGY SOURCES
FUEL REPROCESSING PLANTS
FUELS
GRAPHITE
MATERIALS
METALS
MINERALS
NICKEL
NONMETALS
NUCLEAR FACILITIES
NUCLEAR FUELS
REACTOR MATERIALS
SEPARATION PROCESSES
SPENT FUELS
TIN
TRANSITION ELEMENTS