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

Abstract

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.

Inventors:
Issue Date:
OSTI Identifier:
5720288
Application Number:
ON: DE82004441
Assignee:
TIC; NTS-82-003978; ERA-07-029218; EDB-82-069628
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; SPENT FUELS; REPROCESSING; CARBONITRIDES; COMPLEXES; DENATURED FUEL; FISSION PRODUCTS; MIXED OXIDE FUELS; MIXTURES; NITRATES; PLUTONIUM CARBIDES; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; PUREX PROCESS; SOL-GEL PROCESS; STABILIZATION; URANIUM CARBIDES; URANIUM COMPOUNDS; URANIUM OXIDES; ACTINIDE COMPOUNDS; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; DISPERSIONS; ENERGY SOURCES; FUELS; ISOTOPES; MATERIALS; NITROGEN COMPOUNDS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; SEPARATION PROCESSES; SOLID FUELS; TRANSURANIUM COMPOUNDS; 050800* - Nuclear Fuels- Spent Fuels Reprocessing

Citation Formats

Lloyd, M.H. Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides. United States: N. p., 1981. Web.
Lloyd, M.H. Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides. United States.
Lloyd, M.H. Fri . "Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides". United States.
@article{osti_5720288,
title = {Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides},
author = {Lloyd, M.H.},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1981},
month = {1}
}