Separation by solvent extraction
Abstract
17. A process for separating fission product values from uranium and plutonium values contained in an aqueous solution, comprising adding an oxidizing agent to said solution to secure uranium and plutonium in their hexavalent state; contacting said aqueous solution with a substantially water-immiscible organic solvent while agitating and maintaining the temperature at from -1.degree. to -2.degree. C. until the major part of the water present is frozen; continuously separating a solid ice phase as it is formed; separating a remaining aqueous liquid phase containing fission product values and a solvent phase containing plutonium and uranium values from each other; melting at least the last obtained part of said ice phase and adding it to said separated liquid phase; and treating the resulting liquid with a new supply of solvent whereby it is practically depleted of uranium and plutonium.
- Inventors:
-
- (Kennewick, WA)
- Issue Date:
- Research Org.:
- Knolls Atomic Power Lab
- OSTI Identifier:
- 862495
- Patent Number(s):
- 3949048
- Assignee:
- United States of America as represented by United States 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:
- W-31-109-ENG-52
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- separation; solvent; extraction; 17; process; separating; fission; product; values; uranium; plutonium; contained; aqueous; solution; comprising; adding; oxidizing; agent; secure; hexavalent; contacting; substantially; water-immiscible; organic; agitating; maintaining; temperature; -1; degree; -2; major; water; frozen; continuously; solid; ice; phase; formed; remaining; liquid; containing; melting; obtained; separated; treating; resulting; supply; whereby; practically; depleted; plutonium values; solvent phase; values contained; phase containing; fission product; solvent extraction; organic solvent; aqueous solution; liquid phase; oxidizing agent; aqueous liquid; product values; uranium values; resulting liquid; water-immiscible organic; containing plutonium; immiscible organic; oxidizing agen; solvent extract; /423/976/
Citation Formats
Holt, Jr., Charles H. Separation by solvent extraction. United States: N. p., 1976.
Web.
Holt, Jr., Charles H. Separation by solvent extraction. United States.
Holt, Jr., Charles H. Tue .
"Separation by solvent extraction". United States. https://www.osti.gov/servlets/purl/862495.
@article{osti_862495,
title = {Separation by solvent extraction},
author = {Holt, Jr., Charles H.},
abstractNote = {17. A process for separating fission product values from uranium and plutonium values contained in an aqueous solution, comprising adding an oxidizing agent to said solution to secure uranium and plutonium in their hexavalent state; contacting said aqueous solution with a substantially water-immiscible organic solvent while agitating and maintaining the temperature at from -1.degree. to -2.degree. C. until the major part of the water present is frozen; continuously separating a solid ice phase as it is formed; separating a remaining aqueous liquid phase containing fission product values and a solvent phase containing plutonium and uranium values from each other; melting at least the last obtained part of said ice phase and adding it to said separated liquid phase; and treating the resulting liquid with a new supply of solvent whereby it is practically depleted of uranium and plutonium.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Apr 06 00:00:00 EST 1976},
month = {Tue Apr 06 00:00:00 EST 1976}
}