Separation of uranium from technetium in recovery of spent nuclear fuel
Abstract
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.
- Inventors:
- Issue Date:
- OSTI Identifier:
- 6002567
- Application Number:
- ON: TI85006499
- Assignee:
- Dept. of Energy
- DOE Contract Number:
- AC05-84OR21400
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; TECHNETIUM; SOLVENT EXTRACTION; URANIUM; DECONTAMINATION; HYDRAZINE; OXALIC ACID; PUREX PROCESS; TBP; URANYL NITRATES; ACTINIDE COMPOUNDS; ACTINIDES; BUTYL PHOSPHATES; CARBOXYLIC ACIDS; CLEANING; DICARBOXYLIC ACIDS; ELEMENTS; ESTERS; EXTRACTION; METALS; NITRATES; NITROGEN COMPOUNDS; ORGANIC ACIDS; ORGANIC COMPOUNDS; ORGANIC PHOSPHORUS COMPOUNDS; OXYGEN COMPOUNDS; PHOSPHORIC ACID ESTERS; REPROCESSING; SEPARATION PROCESSES; TRANSITION ELEMENTS; URANIUM COMPOUNDS; URANYL COMPOUNDS; 050800* - Nuclear Fuels- Spent Fuels Reprocessing; 400105 - Separation Procedures
Citation Formats
Friedman, H A. Separation of uranium from technetium in recovery of spent nuclear fuel. United States: N. p., 1984.
Web.
Friedman, H A. Separation of uranium from technetium in recovery of spent nuclear fuel. United States.
Friedman, H A. Wed .
"Separation of uranium from technetium in recovery of spent nuclear fuel". United States.
@article{osti_6002567,
title = {Separation of uranium from technetium in recovery of spent nuclear fuel},
author = {Friedman, H A},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1984},
month = {6}
}
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