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Title: Method for reprocessing and separating spent nuclear fuels

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.
Authors:
 [1] ;  [2] ;  [3]
  1. (Danville, CA)
  2. (Livermore, CA)
  3. (Walnut Creek, CA)
Publication Date:
OSTI Identifier:
864669
Report Number(s):
US 4399108
DOE Contract Number:
W-7405-ENG-48
Resource Type:
Patent
Research Org:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA
Country of Publication:
United States
Language:
English
Subject:
method; reprocessing; separating; spent; nuclear; fuels; spent; nuclear; fuels; including; actinide; fuels; volatile; non-volatile; fission; products; reprocessed; separated; molten; metal; solvent; housed; separation; vessel; carbon-containing; material; catalyst; promotes; solubility; permeability; carbon; metal; solvent; included; increasing; solubility; permeability; carbon; solvent; rate; actinide; oxides; reduced; carbothermic; reduction; greatly; increased; catalyst; included; increase; affinity; nitrogen; metal; solvent; added; increase; rate; actinide; nitrides; form; carbothermic; reduction; complete; carbothermic reduction; carbothermic reduction; nuclear fuels; nuclear fuels; fission product; fission products; nuclear fuel; nuclear fuel; molten metal; spent nuclear; spent nuclear; greatly increased; carbon-containing material; separation vessel; containing material; actinide oxide; volatile fission; greatly increase; actinide fuel; actinide nitrides /423/75/976/