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

Patent ·
OSTI ID:6749349

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
Application Number:
ON: DE83002352
OSTI ID:
6749349
Country of Publication:
United States
Language:
English