Method for reprocessing and separating spent nuclear fuels

Patent · Sat Jan 01 00:00:00 EST 1983

OSTI ID:864669

Krikorian, Oscar H ^[1]; Grens, John Z ^[2]

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1. Danville, CA
2. Livermore, CA

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.

• Research Organization: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
• DOE Contract Number: W-7405-ENG-48
• Assignee: Krikorian, Oscar H. (Danville, CA);Grens, John Z. (Livermore, CA);Parrish, Sr., William H. (Walnut Creek, CA)
• Patent Number(s): US 4399108
• OSTI ID: 864669
• Country of Publication: United States
• Language: English

Related Subjects

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/