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

Patent · Tue Jan 19 04:00:00 EST 1982

OSTI ID:6749350

Krikorian, O H; Grens, J Z; Parrish, Sr, W H; Coops, M S

A method and apparatus for separating and reprocessing spent nuclear fuels includes a separation vessel housing a molten metal solvent in a reaction region, a reflux region positioned above and adjacent to the reaction region, and a porous filter member defining the bottom of the separation vessel in a supporting relationship with the metal solvent. Spent fuels are added to the metal solvent. A nonoxidizing nitrogen-containing gas is introduced into the separation vessel, forming solid actinide nitrides in the metal solvent from actinide fuels, while leaving other fission products in solution. A pressure of about 1.1 to 1.2 atm is applied in the reflux region, forcing the molten metal solvent and soluble fission products out of the vessel, while leaving the solid actinide nitrides in the separation vessel.

• DOE Contract Number: W-7405-ENG-48
• Assignee: Dept. of Energy
• Patent Number(s): None
• Application Number: ON: DE83002357
• OSTI ID: 6749350
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
CHEMICAL REACTIONS
ELEMENTS
ENERGY SOURCES
FILTERS
FILTRATION
FISSION PRODUCTS
FLUIDS
FUELS
ISOTOPES
LIQUID METALS
LIQUIDS
MATERIALS
METALS
NITRIDATION
NITROGEN
NONMETALS
NUCLEAR FUELS
POROUS MATERIALS
PYROCHEMICAL REPROCESSING
RADIOACTIVE MATERIALS
REACTOR MATERIALS
REPROCESSING
SEPARATION PROCESSES
SPENT FUELS
TIN