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Title: 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:
 [1];  [1];  [1]
  1. (Oak Ridge, TN)
Issue Date:
Research Org.:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN
OSTI Identifier:
864390
Patent Number(s):
4358426
Assignee:
United States of America as represented by United States (Washington, DC) ORNL
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 = {1982},
month = {1}
}

Patent:

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