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

Patent ·
OSTI ID:6749350

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
Application Number:
ON: DE83002357
OSTI ID:
6749350
Country of Publication:
United States
Language:
English