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 Laboratory (ORNL), Oak Ridge, TN

OSTI Identifier:: 865509

Patent Number(s):: 4528165

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

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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Separation of uranium from technetium in recovery of spent nuclear fuel

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Uranium and technetium in the product stream of the Purex process for recovery of uranium in spent nuclear fuel are separated by (1) contacting the aqueous Purex product stream with hydrazine to reduce Tc.sup.+7 therein to a reduced species, and (2) contacting said aqueous stream with an organic phase containing tributyl phosphate and an organic diluent to extract uranium from said aqueous stream into said organic phase.
Full Text Available
Separation of uranium from technetium in recovery of spent nuclear fuel

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A method for decontaminating uranium product from the Purex 5 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 10 uranium by solvent extraction with 30 vol % tributyl phosphate in n-dodecane.
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Uranium and technetium in the product stream of the Purex process for recovery of uranium in spent nuclear fuel are separated by (1) contacting the aqueous Purex product stream with hydrazine to reduce Tc/sup +7/ therein to a reduced species, and (2) contacting said aqueous stream with an organic phase containing tributyl phosphate and an organic diluent to extract uranium from said aqueous stream into said organic phase.
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Patent Pruett, D.J.; McTaggart, D.R.

Uranium and technetium in the product stream of the Purex process for recovery of uranium in spent nuclear fuel are separated by (1) contacting the aqueous Purex product stream with hydrazine to reduce Tc/sup +7/ therein to a reduced species, and (2) contacting said aqueous stream with an organic phase containing tributyl phosphate and an organic diluent to extract uranium from said aqueous stream into said organic phase.

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