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Title: Method for reprocessing and separating spent nuclear fuels

Abstract

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.

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

Citation Formats

Krikorian, Oscar H., Grens, John Z., and Parrish, Sr., William H. Method for reprocessing and separating spent nuclear fuels. United States: N. p., 1983. Web.
Krikorian, Oscar H., Grens, John Z., & Parrish, Sr., William H. Method for reprocessing and separating spent nuclear fuels. United States.
Krikorian, Oscar H., Grens, John Z., and Parrish, Sr., William H. Sat . "Method for reprocessing and separating spent nuclear fuels". United States. https://www.osti.gov/servlets/purl/864669.
@article{osti_864669,
title = {Method for reprocessing and separating spent nuclear fuels},
author = {Krikorian, Oscar H. and Grens, John Z. and Parrish, Sr., William H.},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1983},
month = {1}
}

Patent:

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