PROCESS FOR SEGREGATING URANIUM FROM PLUTONIUM AND FISSION-PRODUCT CONTAMINATION
Abstract
An aqueous nitric acid solution containing uranium, plutonium, and fission product values is contacted with an organic extractant comprised of a trialkyl phosphate and an organic diluent. The relative amounts of trialkyl phosphate and uranium values are controlled to achieve a concentration of uranium values in the organic extractant of at least 0.35 moles uranium per mole of trialkyl phosphate, thereby preferentially extracting uranium values into the organic extractant.
- Inventors:
- Issue Date:
- OSTI Identifier:
- 4005649
- Patent Number(s):
- 2990240
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
- NSA Number:
- NSA-15-019476
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; ALKYL RADICALS; BUTYL PHOSPHATES; CONTAMINATION; FISSION PRODUCTS; NITRIC ACID; ORGANIC COMPOUNDS; PLUTONIUM; SEPARATION PROCESSES; SOLUTIONS; SOLVENT EXTRACTION; URANIUM; WATER
Citation Formats
Ellison, C V, and Runion, T C. PROCESS FOR SEGREGATING URANIUM FROM PLUTONIUM AND FISSION-PRODUCT CONTAMINATION. United States: N. p., 1961.
Web.
Ellison, C V, & Runion, T C. PROCESS FOR SEGREGATING URANIUM FROM PLUTONIUM AND FISSION-PRODUCT CONTAMINATION. United States.
Ellison, C V, and Runion, T C. Tue .
"PROCESS FOR SEGREGATING URANIUM FROM PLUTONIUM AND FISSION-PRODUCT CONTAMINATION". United States.
@article{osti_4005649,
title = {PROCESS FOR SEGREGATING URANIUM FROM PLUTONIUM AND FISSION-PRODUCT CONTAMINATION},
author = {Ellison, C V and Runion, T C},
abstractNote = {An aqueous nitric acid solution containing uranium, plutonium, and fission product values is contacted with an organic extractant comprised of a trialkyl phosphate and an organic diluent. The relative amounts of trialkyl phosphate and uranium values are controlled to achieve a concentration of uranium values in the organic extractant of at least 0.35 moles uranium per mole of trialkyl phosphate, thereby preferentially extracting uranium values into the organic extractant.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {6}
}
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