Method for photochemical reduction of uranyl nitrate by tri-N-butyl phosphate and application of this method to nuclear fuel reprocessing

Title: Method for photochemical reduction of uranyl nitrate by tri-N-butyl phosphate and application of this method to nuclear fuel reprocessing

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Abstract

Uranyl ion in solution in tri-n-butyl phosphate is readily photochemically reduced to U(IV). The product U(IV) may effectively be used in the Purex process for treating spent nuclear fuels to reduce Pu(IV) to Pu(III). The Pu(III) is readily separated from uranium in solution in the tri-n-butyl phosphate by an aqueous strip.

Inventors:

De Poorter, Gerald L ^[1]; Rofer-De Poorter, Cheryl K ^[1]

Los Alamos, NM

Publication Date:: 1978-01-01

Research Org.:: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

OSTI Identifier:: 863040

Patent Number(s):: US 4080273

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

Resource Type:: Patent

Country of Publication:: United States

Language:: English

Subject:: method; photochemical; reduction; uranyl; nitrate; tri-n-butyl; phosphate; application; nuclear; fuel; reprocessing; solution; readily; photochemically; reduced; product; effectively; purex; process; treating; spent; fuels; reduce; iii; separated; uranium; aqueous; strip; readily separated; purex process; tri-n-butyl phosphate; chemically reduce; uranyl nitrate; nuclear fuels; nuclear fuel; spent nuclear; fuel reprocessing; aqueous strip; chemical reduction; chemically reduced; /204/423/976/

Citation Formats


                    De Poorter, Gerald L, and Rofer-De Poorter, Cheryl K. Method for photochemical reduction of uranyl nitrate by tri-N-butyl phosphate and application of this method to nuclear fuel reprocessing.  United States: N. p., 1978. 
        Web.

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                    De Poorter, Gerald L, & Rofer-De Poorter, Cheryl K. Method for photochemical reduction of uranyl nitrate by tri-N-butyl phosphate and application of this method to nuclear fuel reprocessing.  United States.

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                    De Poorter, Gerald L, and Rofer-De Poorter, Cheryl K. Sun .  
        "Method for photochemical reduction of uranyl nitrate by tri-N-butyl phosphate and application of this method to nuclear fuel reprocessing".  United States.  https://www.osti.gov/servlets/purl/863040.

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@article{osti_863040,

  title        = {Method for photochemical reduction of uranyl nitrate by tri-N-butyl phosphate and application of this method to nuclear fuel reprocessing},

  author       = {De Poorter, Gerald L and Rofer-De Poorter, Cheryl K},

  abstractNote = {Uranyl ion in solution in tri-n-butyl phosphate is readily photochemically reduced to U(IV). The product U(IV) may effectively be used in the Purex process for treating spent nuclear fuels to reduce Pu(IV) to Pu(III). The Pu(III) is readily separated from uranium in solution in the tri-n-butyl phosphate by an aqueous strip.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/863040},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1978},

  month        = {1}

}

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Method for photochemical reduction of uranyl nitrate by tri-n-butyl phosphate and application of this method to nuclear fuel processing

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Uranyl ion in solution in tri-n-butyl phosphate is readily photochemically reduced to U(IV). The product U(IV) may effectively be used in the Purex process for treating spent nuclear fuels to reduce Pu(IV) to Pu(III). The Pu(III) is readily separated from uranium in solution in the tri-n-butyl phosphate by an aqueous strip.
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