URANIUM SEPARATION PROCESS
Abstract
The separation of uranium from a mixture of uranium and thorium by organic solvent extraction from an aqueous solution is described. The uranium is separrted from an aqueous mixture of uranium and thorium nitrates 3 N in nitric acid and containing salting out agents such as ammonium nitrate, so as to bring ihe total nitrate ion concentration to a maximum of about 8 N by contacting the mixture with an immiscible aliphatic oxygen containing organic solvent such as diethyl carbinol, hexone, n-amyl acetate and the like. The uranium values may be recovered from the organic phase by back extraction with water.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4236017
- Patent Number(s):
- 2894827
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
- NSA Number:
- NSA-14-002496
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; ACETATES; ALCOHOLS; AMMONIUM COMPOUNDS; AMYL RADICALS; HEXANE; KETONES; MIXING; NITRATES; NITRIC ACID; ORGANIC COMPOUNDS; RECOVERY; SALTING-OUT AGENTS; SEPARATION PROCESSES; SOLUTIONS; SOLVENT EXTRACTION; THORIUM; THORIUM NITRATES; URANIUM; URANIUM NITRATES; WATER
Citation Formats
Hyde, E K, Katzin, L I, and Wolf, M J. URANIUM SEPARATION PROCESS. United States: N. p., 1959.
Web.
Hyde, E K, Katzin, L I, & Wolf, M J. URANIUM SEPARATION PROCESS. United States.
Hyde, E K, Katzin, L I, and Wolf, M J. Tue .
"URANIUM SEPARATION PROCESS". United States.
@article{osti_4236017,
title = {URANIUM SEPARATION PROCESS},
author = {Hyde, E K and Katzin, L I and Wolf, M J},
abstractNote = {The separation of uranium from a mixture of uranium and thorium by organic solvent extraction from an aqueous solution is described. The uranium is separrted from an aqueous mixture of uranium and thorium nitrates 3 N in nitric acid and containing salting out agents such as ammonium nitrate, so as to bring ihe total nitrate ion concentration to a maximum of about 8 N by contacting the mixture with an immiscible aliphatic oxygen containing organic solvent such as diethyl carbinol, hexone, n-amyl acetate and the like. The uranium values may be recovered from the organic phase by back extraction with water.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {7}
}
Search for the full text at the U.S. Patent and Trademark Office
Note: You will be redirected to the USPTO site, which may require a pop-up blocker to be deactivated to view the patent. If so, you will need to manually turn off your browser's pop-up blocker, typically found within the browser settings. (See DOE Patents FAQs for more information.)
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.