Method for photochemical reduction of uranyl nitrate by tri-N-butyl phosphate and application of this method to nuclear fuel reprocessing
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:
-
- Los Alamos, NM
- Issue Date:
- 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):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21F - PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT
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
- 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.
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.
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.
@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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