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Title: Solvent wash solution

Abstract

Process for removing diluent degradation products from a solvent extraction solution, which has been used to recover uranium and plutonium from spent nuclear fuel. A wash solution and the solvent extraction solution are combined. The wash solution contains (a) water and (b) up to about, and including, 50 volume percent of at least one-polar water-miscible organic solvent based on the total volume of the water and the highly-polar organic solvent. The wash solution also preferably contains at least one inorganic salt. The diluent degradation products dissolve in the highly-polar organic solvent and the organic solvent extraction solvent do not dissolve in the highly-polar organic solvent. The highly-polar organic solvent and the extraction solvent are separated.

Inventors:
 [1]
  1. Blackville, SC
Issue Date:
Research Org.:
ALLIED-GENERAL NUCLEAR SERVICE
OSTI Identifier:
865881
Patent Number(s):
4595529
Assignee:
United States of America as represented by Department of Energy (Washington, DC)
DOE Contract Number:  
AC09-83SR11036
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
solvent; wash; solution; process; removing; diluent; degradation; products; extraction; recover; uranium; plutonium; spent; nuclear; fuel; combined; contains; water; including; 50; volume; percent; one-polar; water-miscible; organic; based; total; highly-polar; preferably; inorganic; salt; dissolve; separated; preferably contains; preferably contain; polar organic; total volume; extraction solvent; solvent extraction; volume percent; organic solvent; nuclear fuel; spent nuclear; degradation products; water-miscible organic; solution contains; organic salt; wash solution; solution process; recover uranium; extraction solution; inorganic salt; solvent wash; solvent extract; /252/210/423/976/

Citation Formats

Neace, James C. Solvent wash solution. United States: N. p., 1986. Web.
Neace, James C. Solvent wash solution. United States.
Neace, James C. Wed . "Solvent wash solution". United States. https://www.osti.gov/servlets/purl/865881.
@article{osti_865881,
title = {Solvent wash solution},
author = {Neace, James C},
abstractNote = {Process for removing diluent degradation products from a solvent extraction solution, which has been used to recover uranium and plutonium from spent nuclear fuel. A wash solution and the solvent extraction solution are combined. The wash solution contains (a) water and (b) up to about, and including, 50 volume percent of at least one-polar water-miscible organic solvent based on the total volume of the water and the highly-polar organic solvent. The wash solution also preferably contains at least one inorganic salt. The diluent degradation products dissolve in the highly-polar organic solvent and the organic solvent extraction solvent do not dissolve in the highly-polar organic solvent. The highly-polar organic solvent and the extraction solvent are separated.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1986},
month = {1}
}

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