Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides

Patent · Thu Jan 08 23:00:00 EST 1981

OSTI ID:5720288

Lloyd, M H

Method for direct coprocessing of nuclear fuels derived from a product stream of fuels reprocessing facility containing uranium, plutonium, and fission product values comprising nitrate stabilization of said stream vacuum concentration to remove water and nitrates, neutralization to form an acid deficient feed solution for the internal gelation mode of sol-gel technology, green spherule formation, recovery and treatment for loading into a fuel element by vibra packed or pellet formation technologies.

• DOE Contract Number: W-7405-ENG-26
• Assignee: TIC; EDB-82-069628; NTS-82-003978; ERA-07-029218
• Patent Number(s): None
• Application Number: ON: DE82004441
• OSTI ID: 5720288
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
CARBONITRIDES
CHALCOGENIDES
COMPLEXES
DENATURED FUEL
DISPERSIONS
ENERGY SOURCES
FISSION PRODUCTS
FUELS
ISOTOPES
MATERIALS
MIXED OXIDE FUELS
MIXTURES
NITRATES
NITROGEN COMPOUNDS
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM CARBIDES
PLUTONIUM COMPOUNDS
PLUTONIUM OXIDES
PUREX PROCESS
RADIOACTIVE MATERIALS
REACTOR MATERIALS
REPROCESSING
SEPARATION PROCESSES
SOL-GEL PROCESS
SOLID FUELS
SPENT FUELS
STABILIZATION
TRANSURANIUM COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM OXIDES