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Title: 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 DTIE; NSA-14-002496
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}
}