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

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

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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:: Lloyd, M.H.

Issue Date:: 1981-01-09

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

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                    Lloyd, M.H. Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides.  United States: N. p., 1981. 
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                    Lloyd, M.H. Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides.  United States.

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                    Lloyd, M.H. Fri .  
        "Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides".  United States.

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@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}

}

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Similar records in DOE Patents and OSTI.GOV collections:

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

Patent Lloyd, M.

A method is disclosed for direct coprocessing of nuclear fuels derived from a product stream of a 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.
Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides

Patent Lloyd, Milton H. (Oak Ridge, TN)

Method for direct coprocessing of nuclear fuels derived from a product stream of a 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.
Full Text Available
HYDROFLUORINATION OF U/Th OXIDES AND CARBIDES WITH A COATING OF PYROCARBON/ SILICON CARBIDE/PYROCARBON IN THE CONTEXT OF DRY REPROCESSING OF NUCLEAR FUELS CONTAINING THORIUM. (in German English)

Journal Article Kreutz, R.; Kuhrt, W.; Massonne, J. - Kerntech. Atomprax. 13: 21-3(Jan 1971).
PROCESS FOR THE PREPARATION OF NUCLEAR FUELS CONTAINING MIXED CARBIDES.

Patent Beucherie, P.; Wurm, J.G.
Self-diffusion processes in nuclear carbonitrides UC/sub x/N/sub 1-x/ and (U,Pu)C/sub 0/ /sub 8/N/sub 0/ /sub 2/

Journal Article Matsui, H.; Bradbury, M.H.; Matzke, J. - Nucl. Sci. Eng.; (United States)

The self-diffusion of /sup 14/C and /sup 233/U in four different uranium carbonitrides, UC/sub x/N/sub 1-x/ with x = 0.67, 0.26, 0.24, and 0.18, and the diffusion of /sup 238/Pu in two sets of (U,Pu)C/sub 0/./sub 8/N/sub 0/./sub 2/ were measured. Replacing carbon by nitrogen decreased self-diffusion rates in both metal and non-metal lattices. The decrease was not linear with x; rather, a change in mechanism or bonding at around x approximately equal to 0.5 was indicated. The data are of importance for both fabrication and reactor operation of carbonitrides.

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