High density UO2 and high thermal conductivity UO2 composites by spark plasma sintering (SPS)

Subhash, Ghatu; Baney, Ronald Howard; Tulenko, James S.; McKenna, Edward; Ge, Lihao; Yeo, Sunghwan

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Title: High density UO2 and high thermal conductivity UO2 composites by spark plasma sintering (SPS)

Abstract

Embodiments of the invention are directed to a method for production of a nuclear fuel pellet by spark plasma sintering (SPS), wherein a fuel pellet with more than 80% TD or more than 90% TD is formed. The SPS can be performed with the imposition of a controlled uniaxial pressure applied at the maximum temperature of the processing to achieve a very high density, in excess of 95% TD, at temperatures of 850 to 1600° C. The formation of a fuel pellet can be carried out in one hour or less. In an embodiment of the invention, a nuclear fuel pellet comprises UO₂ and a highly thermally conductive material, such as SiC or diamond.

Inventors:: Subhash, Ghatu; Baney, Ronald Howard; Tulenko, James S.; McKenna, III, Edward; Ge, Lihao; Yeo, Sunghwan

Issue Date:: 2022-08-09

Research Org.:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1924973

Patent Number(s):: 11410782

Application Number:: 16/996,715

Assignee:: University of Florida Research Foundation, Incorporated (Gainesville, FL)

Patent Classifications (CPCs):: G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS

Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION

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G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
G21C21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
G21C3/045 - {Pellets}
G21C3/62 - Ceramic fuel
G21C3/623 - {Oxide fuels}
G21C3/64 - Ceramic dispersion fuel, e.g. cermet

Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
Y02E30/30 - Nuclear fission reactors

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DOE Contract Number:: AC07-05ID14517

Resource Type:: Patent

Resource Relation:: Patent File Date: 08/18/2020

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats


                    Subhash, Ghatu, Baney, Ronald Howard, Tulenko, James S., McKenna, III, Edward, Ge, Lihao, and Yeo, Sunghwan. High density UO2 and high thermal conductivity UO2 composites by spark plasma sintering (SPS).  United States: N. p., 2022. 
        Web.

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                    Subhash, Ghatu, Baney, Ronald Howard, Tulenko, James S., McKenna, III, Edward, Ge, Lihao, & Yeo, Sunghwan. High density UO2 and high thermal conductivity UO2 composites by spark plasma sintering (SPS).  United States.

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                    Subhash, Ghatu, Baney, Ronald Howard, Tulenko, James S., McKenna, III, Edward, Ge, Lihao, and Yeo, Sunghwan. Tue .  
        "High density UO2 and high thermal conductivity UO2 composites by spark plasma sintering (SPS)".  United States.  https://www.osti.gov/servlets/purl/1924973.

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@article{osti_1924973,

  title        = {High density UO2 and high thermal conductivity UO2 composites by spark plasma sintering (SPS)},

  author       = {Subhash, Ghatu and Baney, Ronald Howard and Tulenko, James S. and McKenna, III, Edward and Ge, Lihao and Yeo, Sunghwan},

  abstractNote = {Embodiments of the invention are directed to a method for production of a nuclear fuel pellet by spark plasma sintering (SPS), wherein a fuel pellet with more than 80% TD or more than 90% TD is formed. The SPS can be performed with the imposition of a controlled uniaxial pressure applied at the maximum temperature of the processing to achieve a very high density, in excess of 95% TD, at temperatures of 850 to 1600° C. The formation of a fuel pellet can be carried out in one hour or less. In an embodiment of the invention, a nuclear fuel pellet comprises UO2 and a highly thermally conductive material, such as SiC or diamond.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {2022},

  month        = {8}

}

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Similar Records

Title: High density UO2 and high thermal conductivity UO2 composites by spark plasma sintering (SPS)

Abstract

Citation Formats

Thermal conductivity of diamond particle dispersed aluminum matrix composites fabricated in solid–liquid co-existent state by SPS journal, July 2011

Uranium Dioxide Article and Method of Producing the Same patent, September 1971

Composite Nuclear Fuel Pellet patent-application, July 2012

Sintering uranium oxide in the reaction products of hydrogen-carbon dioxide mixtures patent, March 1975

Method of preparing nuclear fuel pellet including thermal conductive metal and nuclear fuel pellet prepared thereby patent-application, December 2016

Silicon carbide as an inert-matrix for a thermal reactor fuel journal, August 1999

Process for preparing a large-grained UO.sub.2 fuel patent, December 1989

Microwave versus conventional sintering: A review of fundamentals, advantages and applications journal, April 2010

Spark Plasma Sintering as a Useful Technique to the Nanostructuration of Piezo-Ferroelectric Materials journal, August 2009

Fabrication method for UO2 pellets with large grains or a single grain by sintering in air journal, April 2008

Nuclear Reactor Fuel patent, November 1967

Grain size control of UO2 pellets by adding heat-treated U3O8 particles to UO2 powder journal, May 2003

Thermonuclear plasma reactor for rocket thrust and electrical generation patent-application, January 2009

Method of manufacturing large-grained uranium dioxide fuel pellets containing U3O8 patent, June 2001

Thermal and mechanical properties of uranium nitride prepared by SPS technique journal, October 2008

Enhanced Thermal Conductivity for LWR Fuel journal, January 2010

Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS) journal, April 2013

Enhanced thermal conductivity of uranium dioxide–silicon carbide composite fuel pellets prepared by Spark Plasma Sintering (SPS) journal, February 2013

Refractory Oxides Doped with Silicon Carbide and Silicon Nitride patent, September 1967

Breeding Nuclear Fuel Mixture Using Metallic Thorium patent-application, December 2011

Process for enriching uranium containing feed material patent-application, September 2008

Process for Sintering Uranium Nitride with a Sintering Aid Depressant patent, October 1965

Monitoring and Management of Distributing Information Systems patent-application, January 2008

Synthesis and Low Temperature In Situ Sintering of Uranium Oxide Nanoparticles journal, December 2011

Thermophysical properties of uranium dioxide journal, March 2000

Manufacture of sintered uranium dioxide patent, May 1993

Thermal conductivity of diamond particle dispersed aluminum matrix composites fabricated in solid–liquid co-existent state by SPS
journal, July 2011

Uranium Dioxide Article and Method of Producing the Same
patent, September 1971

Composite Nuclear Fuel Pellet
patent-application, July 2012

Sintering uranium oxide in the reaction products of hydrogen-carbon dioxide mixtures
patent, March 1975

Method of preparing nuclear fuel pellet including thermal conductive metal and nuclear fuel pellet prepared thereby
patent-application, December 2016

Silicon carbide as an inert-matrix for a thermal reactor fuel
journal, August 1999

Process for preparing a large-grained UO.sub.2 fuel
patent, December 1989

Microwave versus conventional sintering: A review of fundamentals, advantages and applications
journal, April 2010

Spark Plasma Sintering as a Useful Technique to the Nanostructuration of Piezo-Ferroelectric Materials
journal, August 2009

Fabrication method for UO2 pellets with large grains or a single grain by sintering in air
journal, April 2008

Nuclear Reactor Fuel
patent, November 1967

Grain size control of UO2 pellets by adding heat-treated U3O8 particles to UO2 powder
journal, May 2003

Thermonuclear plasma reactor for rocket thrust and electrical generation
patent-application, January 2009

Method of manufacturing large-grained uranium dioxide fuel pellets containing U3O8
patent, June 2001

Thermal and mechanical properties of uranium nitride prepared by SPS technique
journal, October 2008

Enhanced Thermal Conductivity for LWR Fuel
journal, January 2010

Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS)
journal, April 2013

Enhanced thermal conductivity of uranium dioxide–silicon carbide composite fuel pellets prepared by Spark Plasma Sintering (SPS)
journal, February 2013

Refractory Oxides Doped with Silicon Carbide and Silicon Nitride
patent, September 1967

Breeding Nuclear Fuel Mixture Using Metallic Thorium
patent-application, December 2011

Process for enriching uranium containing feed material
patent-application, September 2008

Process for Sintering Uranium Nitride with a Sintering Aid Depressant
patent, October 1965

Monitoring and Management of Distributing Information Systems
patent-application, January 2008

Synthesis and Low Temperature In Situ Sintering of Uranium Oxide Nanoparticles
journal, December 2011

Thermophysical properties of uranium dioxide
journal, March 2000

Manufacture of sintered uranium dioxide
patent, May 1993