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

De Poorter, Gerald L; Rofer-De Poorter, Cheryl K

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

Issue Date:: 1978-01-01

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

OSTI Identifier:: 863040

Patent Number(s):: 4080273

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

Patent Classifications (CPCs):: 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

G - PHYSICS G21 - NUCLEAR PHYSICS G21F - PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT

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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

G - PHYSICS G21 - NUCLEAR PHYSICS G21F - PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT
G21F9/007 - {Recovery of isotopes from radioactive waste, e.g. fission products

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 Y02W - CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
Y02W30/50 - Reuse, recycling or recovery technologies

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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          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1978},

  month        = {1}

}

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