Separation of uranium from technetium in recovery of spent nuclear fuel
Abstract
A method for decontaminating uranium product from the Purex 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 uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.
- Inventors:
-
- Oak Ridge, TN
- Issue Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- OSTI Identifier:
- 865509
- Patent Number(s):
- 4528165
- Assignee:
- United States of America as represented by United States (Washington, DC)
- Patent Classifications (CPCs):
-
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
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
- DOE Contract Number:
- W-7405-ENG-26
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- separation; uranium; technetium; recovery; spent; nuclear; fuel; method; decontaminating; product; purex; process; comprises; addition; hydrazine; uranyl; nitrate; stream; contains; hexavalent; uo; heptavalent; tco; reduced; complexed; oxalic; acid; tc-oxalate; complex; readily; separated; solvent; extraction; 30; vol; tributyl; phosphate; n-dodecane; readily separated; purex process; uranyl nitrate; oxalic acid; tributyl phosphate; product stream; solvent extraction; nuclear fuel; spent nuclear; process comprises; uranium product; solvent extract; /423/976/
Citation Formats
Friedman, Horace A. Separation of uranium from technetium in recovery of spent nuclear fuel. United States: N. p., 1985.
Web.
Friedman, Horace A. Separation of uranium from technetium in recovery of spent nuclear fuel. United States.
Friedman, Horace A. Tue .
"Separation of uranium from technetium in recovery of spent nuclear fuel". United States. https://www.osti.gov/servlets/purl/865509.
@article{osti_865509,
title = {Separation of uranium from technetium in recovery of spent nuclear fuel},
author = {Friedman, Horace A},
abstractNote = {A method for decontaminating uranium product from the Purex 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 uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1985},
month = {1}
}