Method for cleaning solution used in nuclear fuel reprocessing
Abstract
Nuclear fuel processing solution consisting of tri-n-butyl phosphate and dodecane, with a complex of uranium, plutonium, or zirconium and with a solvent degradation product such as di-n-butyl phosphate therein, is contacted with an aqueous solution of a salt formed from hydrazine and either a dicarboxylic acid or a hydroxycarboxylic acid, thereby removing the aforesaid complex from the processing solution.
- Inventors:
-
- Oak Ridge, TN
- Issue Date:
- Research Org.:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- OSTI Identifier:
- 864390
- Patent Number(s):
- 4358426
- Assignee:
- United States of America as represented by United States (Washington, DC)
- Patent Classifications (CPCs):
-
C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01G - COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- method; cleaning; solution; nuclear; fuel; reprocessing; processing; consisting; tri-n-butyl; phosphate; dodecane; complex; uranium; plutonium; zirconium; solvent; degradation; product; di-n-butyl; therein; contacted; aqueous; salt; formed; hydrazine; dicarboxylic; acid; hydroxycarboxylic; removing; aforesaid; tri-n-butyl phosphate; fuel processing; nuclear fuel; aqueous solution; carboxylic acid; solution consisting; fuel reprocessing; processing solution; cleaning solution; dicarboxylic acid; salt form; /423/976/
Citation Formats
Tallent, Othar K, Crouse, David J, and Mailen, James C. Method for cleaning solution used in nuclear fuel reprocessing. United States: N. p., 1982.
Web.
Tallent, Othar K, Crouse, David J, & Mailen, James C. Method for cleaning solution used in nuclear fuel reprocessing. United States.
Tallent, Othar K, Crouse, David J, and Mailen, James C. Fri .
"Method for cleaning solution used in nuclear fuel reprocessing". United States. https://www.osti.gov/servlets/purl/864390.
@article{osti_864390,
title = {Method for cleaning solution used in nuclear fuel reprocessing},
author = {Tallent, Othar K and Crouse, David J and Mailen, James C},
abstractNote = {Nuclear fuel processing solution consisting of tri-n-butyl phosphate and dodecane, with a complex of uranium, plutonium, or zirconium and with a solvent degradation product such as di-n-butyl phosphate therein, is contacted with an aqueous solution of a salt formed from hydrazine and either a dicarboxylic acid or a hydroxycarboxylic acid, thereby removing the aforesaid complex from the processing solution.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 1982},
month = {Fri Jan 01 00:00:00 EST 1982}
}
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