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:
-
- 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)
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21F - PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT
- 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 = {Wed Jan 01 00:00:00 EST 1986},
month = {Wed Jan 01 00:00:00 EST 1986}
}