Compositions and methods for treating nuclear fuel

Soderquist, Chuck Z; Johnsen, Amanda M; McNamara, Bruce K; Hanson, Brady D; Smith, Steven C; Peper, Shane M

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Title: Compositions and methods for treating nuclear fuel

Abstract

Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

Inventors:: Soderquist, Chuck Z; Johnsen, Amanda M; McNamara, Bruce K; Hanson, Brady D; Smith, Steven C; Peper, Shane M

Issue Date:: Tue Jan 28 00:00:00 EST 2014

Research Org.:: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1118256

Patent Number(s):: 8636966

Application Number:: 13/964,914

Assignee:: Battelle Memorial Institute (Richland, WA)

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
G21C19/46 - Aqueous processes {, e.g. by using organic extraction means, including the regeneration of these means}
G21C19/48 - Non-aqueous processes

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

Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02W - CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
Y02W30/50 - Reuse, recycling or recovery technologies

Show less

DOE Contract Number:: AC05-76RLO1830

Resource Type:: Patent

Resource Relation:: Patent File Date: 2013 Aug 12

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats


                    Soderquist, Chuck Z, Johnsen, Amanda M, McNamara, Bruce K, Hanson, Brady D, Smith, Steven C, and Peper, Shane M. Compositions and methods for treating nuclear fuel.  United States: N. p., 2014. 
        Web.

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                    Soderquist, Chuck Z, Johnsen, Amanda M, McNamara, Bruce K, Hanson, Brady D, Smith, Steven C, & Peper, Shane M. Compositions and methods for treating nuclear fuel.  United States.

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                    Soderquist, Chuck Z, Johnsen, Amanda M, McNamara, Bruce K, Hanson, Brady D, Smith, Steven C, and Peper, Shane M. Tue .  
        "Compositions and methods for treating nuclear fuel".  United States.  https://www.osti.gov/servlets/purl/1118256.

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@article{osti_1118256,

  title        = {Compositions and methods for treating nuclear fuel},

  author       = {Soderquist, Chuck Z and Johnsen, Amanda M and McNamara, Bruce K and Hanson, Brady D and Smith, Steven C and Peper, Shane M},

  abstractNote = {Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Tue Jan 28 00:00:00 EST 2014},

  month        = {Tue Jan 28 00:00:00 EST 2014}

}

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Works referenced in this record:

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Similar Records

Title: Compositions and methods for treating nuclear fuel

Abstract

Citation Formats

Process for recovering molybdenum-99 from a matrix containing neutron irradiated fissionable materials and fission products patent, June 1978

In situ carbonate leaching and recovery of uranium from ore deposits patent, May 1979

Production of molybdenum oxide from ammonium molybdate solutions patent, June 1981

Method of controlling the molybdenum content of uranium yellowcake patent, December 1981

Removal of molybdenum from uranium solutions patent, December 1982

Process for the separation and recovery of molybdenum and uranium from leach solution using ion exchange patent, March 1983

Removal of uranium from sulphate solutions containing molybdenum patent, September 1983

Heated ion exchange process for the recovery of uranium patent, February 1984

Method of precipitating contaminants in a uranium leachate using ferri ions, complexing agent, and pH control patent, August 1984

Uranium recovery from carbonate leach liquors using carboxylic acid cation exchange resin patent, August 1986

Process for the separation of molybdenum by a resin route patent, January 1990

Actinide dissolution patent, April 1993

Method of separating fission molybdenum patent, April 1996

Inorganic sorbent for molybdenum-99 extraction from irradiated uranium solutions and its method of use patent, January 2002

Method of separation and recovery of elements from radioactive liquid wastes patent-application, December 2003

Process for Recovering Isolated Uranium From Spent Nuclear Fuel Using a Highly Alkaline Carbonate Solution patent-application, October 2009

Dissolution study of spent PWR fuel: Dissolution behavior and chemical properties of insoluble residues journal, November 1990

New Approach to the Nuclear Fuel Reprocessing in Non-acidic Aqueous Solutions journal, October 2001

Formation of the ammonium-uranyl-carbonate complexes of the type (NH4)4[UO2(CO3)3], prepared by precipitative re-extraction journal, January 1984

Metallic fission-product inclusions in irradiated oxide fuels journal, February 1968

Precipitation studies of ammonium uranyl carbonate from UO2F2 solutions journal, May 1989

Formation of Studtite during the Oxidative Dissolution of UO 2 by Hydrogen Peroxide: A SFM Study journal, December 2004

Actinide Carbonte Complexes and Their Importance in Actinide Environmental Chemistry journal, January 1995

The chemical effects of composition changes in irradiated oxide fuel materials journal, November 1971

The oxidative dissolution mechanism of uranium dioxide. I. The effect of temperature in hydrogen carbonate medium journal, October 1999

Evaluation of Process That Might Lead to Separation of Actinides in Waste Storage Tanks Under Alkaline Conditions journal, January 2000

Surface electrochemistry of UO2 in dilute alkaline hydrogen peroxide solutions: Part II. Effects of carbonate ions journal, April 2006

The alizarin-S spot test for aluminium in the presence of zirconium, in systematic qualitative analysis journal, September 1964

Recovery of Uranium from Ammonium Uranyl Carbonate (AUC) Effluents by Combined Ion Exchange and Membrane Separation journal, January 2005

Microanalysis of inclusions in irradiated UO2 journal, April 1967

Study on Electrolytic Recoveries of Carbonate Salt and Uranium from a Uranyl Peroxo Carbonato Complex Solution Generated from a Carbonate-Leaching Process journal, February 2009

X-ray diffraction studies on irradiated nuclear fuels journal, May 1984

The chemical state of the fission products in oxide fuels journal, April 1985

Uranium recovery from industrial effluent by ion exchange—column experiments journal, November 2005

Conversion of UF6 to UO2: A quasi-optimization of the ammonium uranyl carbonate process journal, November 1991

On the dependence of characteristics of powders on the AUC process parameters journal, February 1991

Preparation and properties of complex carbonates of hexavalent actinides journal, May 1983

Carbonate Leaching of Uranium from Contaminated Soils journal, October 1997

UO2 dissolution in the presence of hydrogen peroxide at pH>11 journal, January 2008

Analysis of fission product ingots formed in uranium-plutonium oxide irradiated in EBR-II journal, June 1970

Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron flux journal, January 1969

The conversion of UO2 via ammonium uranyl carbonate: Study of precipitation, chemical variation and powder properties journal, September 1981

Kinetic Study of the Oxidative Dissolution of UO 2 in Aqueous Carbonate Media journal, December 2004

Experimental determination of UO2(cr) dissolution kinetics: Effects of solution saturation state and pH journal, October 2005

Fuel corrosion processes under waste disposal conditions journal, November 2000

Dissolution of spent nuclear fuel in carbonate–peroxide solution journal, January 2010

Corrosion of uranium dioxide in hydrogen peroxide solutions journal, May 2004

The isolation of 99Mo from fission material for use in the 99Mo/99mTc generator for medical use journal, January 2004

Process for recovering molybdenum-99 from a matrix containing neutron irradiated fissionable materials and fission products
patent, June 1978

In situ carbonate leaching and recovery of uranium from ore deposits
patent, May 1979

Production of molybdenum oxide from ammonium molybdate solutions
patent, June 1981

Method of controlling the molybdenum content of uranium yellowcake
patent, December 1981

Removal of molybdenum from uranium solutions
patent, December 1982

Process for the separation and recovery of molybdenum and uranium from leach solution using ion exchange
patent, March 1983

Removal of uranium from sulphate solutions containing molybdenum
patent, September 1983

Heated ion exchange process for the recovery of uranium
patent, February 1984

Method of precipitating contaminants in a uranium leachate using ferri ions, complexing agent, and pH control
patent, August 1984

Uranium recovery from carbonate leach liquors using carboxylic acid cation exchange resin
patent, August 1986

Process for the separation of molybdenum by a resin route
patent, January 1990

Actinide dissolution
patent, April 1993

Method of separating fission molybdenum
patent, April 1996

Inorganic sorbent for molybdenum-99 extraction from irradiated uranium solutions and its method of use
patent, January 2002

Method of separation and recovery of elements from radioactive liquid wastes
patent-application, December 2003

Process for Recovering Isolated Uranium From Spent Nuclear Fuel Using a Highly Alkaline Carbonate Solution
patent-application, October 2009

Dissolution study of spent PWR fuel: Dissolution behavior and chemical properties of insoluble residues
journal, November 1990

New Approach to the Nuclear Fuel Reprocessing in Non-acidic Aqueous Solutions
journal, October 2001

Formation of the ammonium-uranyl-carbonate complexes of the type (NH₄)₄[UO₂(CO₃)₃], prepared by precipitative re-extraction
journal, January 1984

Metallic fission-product inclusions in irradiated oxide fuels
journal, February 1968

Precipitation studies of ammonium uranyl carbonate from UO₂F₂ solutions
journal, May 1989

Formation of Studtite during the Oxidative Dissolution of UO ₂ by Hydrogen Peroxide: A SFM Study
journal, December 2004

Actinide Carbonte Complexes and Their Importance in Actinide Environmental Chemistry
journal, January 1995

The chemical effects of composition changes in irradiated oxide fuel materials
journal, November 1971

The oxidative dissolution mechanism of uranium dioxide. I. The effect of temperature in hydrogen carbonate medium
journal, October 1999

Evaluation of Process That Might Lead to Separation of Actinides in Waste Storage Tanks Under Alkaline Conditions
journal, January 2000

Surface electrochemistry of UO₂ in dilute alkaline hydrogen peroxide solutions: Part II. Effects of carbonate ions
journal, April 2006

The alizarin-S spot test for aluminium in the presence of zirconium, in systematic qualitative analysis
journal, September 1964

Recovery of Uranium from Ammonium Uranyl Carbonate (AUC) Effluents by Combined Ion Exchange and Membrane Separation
journal, January 2005

Microanalysis of inclusions in irradiated UO₂
journal, April 1967

Study on Electrolytic Recoveries of Carbonate Salt and Uranium from a Uranyl Peroxo Carbonato Complex Solution Generated from a Carbonate-Leaching Process
journal, February 2009

X-ray diffraction studies on irradiated nuclear fuels
journal, May 1984

The chemical state of the fission products in oxide fuels
journal, April 1985

Uranium recovery from industrial effluent by ion exchange—column experiments
journal, November 2005

Conversion of UF₆ to UO₂: A quasi-optimization of the ammonium uranyl carbonate process
journal, November 1991

On the dependence of characteristics of powders on the AUC process parameters
journal, February 1991

Preparation and properties of complex carbonates of hexavalent actinides
journal, May 1983

Carbonate Leaching of Uranium from Contaminated Soils
journal, October 1997

UO2 dissolution in the presence of hydrogen peroxide at pH>11
journal, January 2008

Analysis of fission product ingots formed in uranium-plutonium oxide irradiated in EBR-II
journal, June 1970

Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron flux
journal, January 1969

The conversion of UO₂ via ammonium uranyl carbonate: Study of precipitation, chemical variation and powder properties
journal, September 1981

Kinetic Study of the Oxidative Dissolution of UO ₂ in Aqueous Carbonate Media
journal, December 2004

Experimental determination of UO₂(cr) dissolution kinetics: Effects of solution saturation state and pH
journal, October 2005

Fuel corrosion processes under waste disposal conditions
journal, November 2000

Dissolution of spent nuclear fuel in carbonate–peroxide solution
journal, January 2010

Corrosion of uranium dioxide in hydrogen peroxide solutions
journal, May 2004

The isolation of ⁹⁹Mo from fission material for use in the ⁹⁹Mo/^99mTc generator for medical use
journal, January 2004