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

Patent · Sun Jan 01 00:00:00 EST 1978

OSTI ID:863040

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

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1. Los Alamos, NM

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.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• Assignee: United States of America as represented by United States (Washington, DC)
• Patent Number(s): US 4080273
• OSTI ID: 863040
• Country of Publication: United States
• Language: English

Related Subjects

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
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