Low temperature chemical processing of graphite-clad nuclear fuels

Pierce, Robert A.

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Title: Low temperature chemical processing of graphite-clad nuclear fuels

Abstract

A reduced-temperature method for treatment of a fuel element is described. The method includes molten salt treatment of a fuel element with a nitrate salt. The nitrate salt can oxidize the outer graphite matrix of a fuel element. The method can also include reduced temperature degradation of the carbide layer of a fuel element and low temperature solubilization of the fuel in a kernel of a fuel element.

Inventors:: Pierce, Robert A.

Issue Date:: Tue Oct 17 00:00:00 EDT 2017

Research Org.:: Savannah River Site (SRS), Aiken, SC (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1399896

Patent Number(s):: 9793019

Application Number:: 14/226,458

Assignee:: Savannah River Nuclear Solutions, LLC

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
G21C19/38 - Chemical means only
G21C21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
G21C3/20 - with coating on fuel or on inside of casing

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:: AC09-08SR22470

Resource Type:: Patent

Resource Relation:: Patent File Date: 2014 Mar 26

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats


                    Pierce, Robert A. Low temperature chemical processing of graphite-clad nuclear fuels.  United States: N. p., 2017. 
        Web.

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                    Pierce, Robert A. Low temperature chemical processing of graphite-clad nuclear fuels.  United States.

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                    Pierce, Robert A. Tue .  
        "Low temperature chemical processing of graphite-clad nuclear fuels".  United States.  https://www.osti.gov/servlets/purl/1399896.

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@article{osti_1399896,

  title        = {Low temperature chemical processing of graphite-clad nuclear fuels},

  author       = {Pierce, Robert A.},

  abstractNote = {A reduced-temperature method for treatment of a fuel element is described. The method includes molten salt treatment of a fuel element with a nitrate salt. The nitrate salt can oxidize the outer graphite matrix of a fuel element. The method can also include reduced temperature degradation of the carbide layer of a fuel element and low temperature solubilization of the fuel in a kernel of a fuel element.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Tue Oct 17 00:00:00 EDT 2017},

  month        = {Tue Oct 17 00:00:00 EDT 2017}

}

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Works referenced in this record:

Production of Sodium Nitrate
patent, December 1950

Stengel, Leonard A.
US Patent Document 2,535,990
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/2535990

Chemical Disintegration and Recovery of Uranium from Sintered Graphite-Uranium Compacts
patent, November 1965

Bradley, M. J.
US Patent Document 3,219,408
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3219408

Processes for the Dissolution of Uranium in Nitric Acid
patent-application, March 1966

Rateau, A.
US Patent Document 3,243,256
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3243256

Method of Reprocessing and/or Separating Nuclear Fuels
patent, May 1967

Vogg, Hubert Heinrich
US Patent Document 3,322,509
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3322509

Method of Decomposing a Nuclear Fuel in a Fused Salt System by Using Nitric Oxide
patent, July 1968

Vogg, Hubert H.; Ochsenfeld, Wilhelm; Bahr, Werner
US Patent Document 3,393,981
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3393981

Method of Treating Coated-Particle Nuclear-Reactor Fuels
patent, October 1968

Knacke, Ottmar; Laser, Manfred
US Patent Document 3,403,985
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3403985

Method for the Extraction of Materials Embedded in a Graphite Body
patent, January 1969

Bildstein, H.
US Patent Document 3,424,564
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3424564

Automatic Toaster
patent, February 1969

Sato, Hosei
US Patent Document 3,426,671
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3426671

Method of and Apparatus for the Treatment of Graphite-Coated Particles for Nuclear Reactors and the Like
patent, July 1969

Schulten, R.
US Patent Document 3,453,090
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3453090

Coated-Particle Fuel and Fertile Element for Nuclear Reactors and Method of Operating Same
patent, June 1972

Boettcher, Alfred
US Patent Document 3,669,832
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/3669832

Process for a gasification of graphite
patent, October 1980

Sugikawa, Susumu; Maeda, Mitsuru; Tsujino, Takeshi
US Patent Document 4,228,141
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/4228141

Process for the separation of coated nuclear fuel particles from a graphitic matrix and installation for implementing the process
patent, March 1985

Kronschnabel, Hartmut; Goerings, Wilhelm; B/o/ lingen, Johann
US Patent Document 4,502,642
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/4502642

Heat-aided method for separating the graphite matrix from the nuclear fuel of nuclear reactor fuel elements
patent, March 1985

Hinssen, Hans-Klemens; Katscher, Werner; Loenissen, Karl-Josef
US Patent Document 4,507,267
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/4507267

Method for disposing of radioactive graphite and silicon carbide in graphite fuel elements
patent, September 1995

Gay, Richard L.
US Patent Document 5,449,505
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/5449505

Encapsulation of spent ceramic nuclear fuel
patent-application, January 2004

Ohkawa, Tihiro
US Patent Document 10/186413; 20040002623
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/20040002623

Process and Targets for Production of No-Carrier-Added Radiotin
patent-application, September 2011

Srivastava, Suresh C.; Zhuikov, Boris Leonidovich; Ermolaev, Stanislav Victorovich
US Patent Document 11/962851; 20110216867
URL: https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/20110216867

Block-type HTGR spent fuel processing: CEA investigation program and initial results
journal, March 2006

Masson, Michel; Grandjean, Stéphane; Lacquement, Jerôme
Nuclear Engineering and Design, Vol. 236, Issue 5-6, p. 516-525
https://doi.org/10.1016/j.nucengdes.2005.11.021

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Similar Records

Title: Low temperature chemical processing of graphite-clad nuclear fuels

Abstract

Citation Formats

Production of Sodium Nitrate patent, December 1950

Chemical Disintegration and Recovery of Uranium from Sintered Graphite-Uranium Compacts patent, November 1965

Processes for the Dissolution of Uranium in Nitric Acid patent-application, March 1966

Method of Reprocessing and/or Separating Nuclear Fuels patent, May 1967

Method of Decomposing a Nuclear Fuel in a Fused Salt System by Using Nitric Oxide patent, July 1968

Method of Treating Coated-Particle Nuclear-Reactor Fuels patent, October 1968

Method for the Extraction of Materials Embedded in a Graphite Body patent, January 1969

Automatic Toaster patent, February 1969

Method of and Apparatus for the Treatment of Graphite-Coated Particles for Nuclear Reactors and the Like patent, July 1969

Coated-Particle Fuel and Fertile Element for Nuclear Reactors and Method of Operating Same patent, June 1972

Process for a gasification of graphite patent, October 1980

Process for the separation of coated nuclear fuel particles from a graphitic matrix and installation for implementing the process patent, March 1985

Heat-aided method for separating the graphite matrix from the nuclear fuel of nuclear reactor fuel elements patent, March 1985

Method for disposing of radioactive graphite and silicon carbide in graphite fuel elements patent, September 1995

Encapsulation of spent ceramic nuclear fuel patent-application, January 2004

Process and Targets for Production of No-Carrier-Added Radiotin patent-application, September 2011

Block-type HTGR spent fuel processing: CEA investigation program and initial results journal, March 2006

Production of Sodium Nitrate
patent, December 1950

Chemical Disintegration and Recovery of Uranium from Sintered Graphite-Uranium Compacts
patent, November 1965

Processes for the Dissolution of Uranium in Nitric Acid
patent-application, March 1966

Method of Reprocessing and/or Separating Nuclear Fuels
patent, May 1967

Method of Decomposing a Nuclear Fuel in a Fused Salt System by Using Nitric Oxide
patent, July 1968

Method of Treating Coated-Particle Nuclear-Reactor Fuels
patent, October 1968

Method for the Extraction of Materials Embedded in a Graphite Body
patent, January 1969

Automatic Toaster
patent, February 1969

Method of and Apparatus for the Treatment of Graphite-Coated Particles for Nuclear Reactors and the Like
patent, July 1969

Coated-Particle Fuel and Fertile Element for Nuclear Reactors and Method of Operating Same
patent, June 1972

Process for a gasification of graphite
patent, October 1980

Process for the separation of coated nuclear fuel particles from a graphitic matrix and installation for implementing the process
patent, March 1985

Heat-aided method for separating the graphite matrix from the nuclear fuel of nuclear reactor fuel elements
patent, March 1985

Method for disposing of radioactive graphite and silicon carbide in graphite fuel elements
patent, September 1995

Encapsulation of spent ceramic nuclear fuel
patent-application, January 2004

Process and Targets for Production of No-Carrier-Added Radiotin
patent-application, September 2011

Block-type HTGR spent fuel processing: CEA investigation program and initial results
journal, March 2006