Separation of uranium from technetium in recovery of spent nuclear fuel

Title: Separation of uranium from technetium in recovery of spent nuclear fuel

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Abstract

A method for decontaminating uranium product from the Purex process comprises addition of hydrazine to the product uranyl nitrate stream from the Purex process, which contains hexavalent (UO.sub.2.sup.2+) uranium and heptavalent technetium (TcO.sub.4 -). Technetium in the product stream is reduced and then complexed by the addition of oxalic acid (H.sub.2 C.sub.2 O.sub.4), and the Tc-oxalate complex is readily separated from the uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.

Inventors:

Friedman, Horace A ^[1]

Oak Ridge, TN

Issue Date:: 1985-01-01

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

OSTI Identifier:: 865509

Patent Number(s):: 4528165

Assignee:: United States of America as represented by United States (Washington, DC)

Patent Classifications (CPCs):: C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS

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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C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
C22B60/026 - {liquid-liquid extraction with or without dissolution in organic solvents}
C22B3/0025 - {using oxalic acids}

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

C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01G - COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
C01G99/003 - {Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange}
C01G99/006 - {Compounds containing, besides a metal not provided for elsewhere in this subclass, two or more other elements other than oxygen or hydrogen

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}

Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02P - CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
Y02P10/20 - Process efficiency

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

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DOE Contract Number:: W-7405-ENG-26

Resource Type:: Patent

Country of Publication:: United States

Language:: English

Subject:: separation; uranium; technetium; recovery; spent; nuclear; fuel; method; decontaminating; product; purex; process; comprises; addition; hydrazine; uranyl; nitrate; stream; contains; hexavalent; uo; heptavalent; tco; reduced; complexed; oxalic; acid; tc-oxalate; complex; readily; separated; solvent; extraction; 30; vol; tributyl; phosphate; n-dodecane; readily separated; purex process; uranyl nitrate; oxalic acid; tributyl phosphate; product stream; solvent extraction; nuclear fuel; spent nuclear; process comprises; uranium product; solvent extract; /423/976/

Citation Formats


                    Friedman, Horace A. Separation of uranium from technetium in recovery of spent nuclear fuel.  United States: N. p., 1985. 
        Web.

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                    Friedman, Horace A. Separation of uranium from technetium in recovery of spent nuclear fuel.  United States.

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                    Friedman, Horace A. Tue .  
        "Separation of uranium from technetium in recovery of spent nuclear fuel".  United States.  https://www.osti.gov/servlets/purl/865509.

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@article{osti_865509,

  title        = {Separation of uranium from technetium in recovery of spent nuclear fuel},

  author       = {Friedman, Horace A},

  abstractNote = {A method for decontaminating uranium product from the Purex process comprises addition of hydrazine to the product uranyl nitrate stream from the Purex process, which contains hexavalent (UO.sub.2.sup.2+) uranium and heptavalent technetium (TcO.sub.4 -). Technetium in the product stream is reduced and then complexed by the addition of oxalic acid (H.sub.2 C.sub.2 O.sub.4), and the Tc-oxalate complex is readily separated from the uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1985},

  month        = {1}

}

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