Solvent extraction system for plutonium colloids and other oxide nano-particles
Abstract
The invention provides a method for extracting plutonium from spent nuclear fuel, the method comprising supplying plutonium in a first aqueous phase; contacting the plutonium aqueous phase with a mixture of a dielectric and a moiety having a first acidity so as to allow the plutonium to substantially extract into the mixture; and contacting the extracted plutonium with second a aqueous phase, wherein the second aqueous phase has a second acidity higher than the first acidity, so as to allow the extracted plutonium to extract into the second aqueous phase. The invented method facilitates isolation of plutonium polymer without the formation of crud or unwanted emulsions.
- Inventors:
- Issue Date:
- Research Org.:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1133666
- Patent Number(s):
- 8741237
- Application Number:
- 12/758,106
- Assignee:
- U.S. Department of Energy (Washington, DC)
- Patent Classifications (CPCs):
-
B - PERFORMING OPERATIONS B01 - PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL B01D - SEPARATION
- DOE Contract Number:
- AC02-06CH11357
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Citation Formats
Soderholm, Lynda, Wilson, Richard E, Chiarizia, Renato, and Skanthakumar, Suntharalingam. Solvent extraction system for plutonium colloids and other oxide nano-particles. United States: N. p., 2014.
Web.
Soderholm, Lynda, Wilson, Richard E, Chiarizia, Renato, & Skanthakumar, Suntharalingam. Solvent extraction system for plutonium colloids and other oxide nano-particles. United States.
Soderholm, Lynda, Wilson, Richard E, Chiarizia, Renato, and Skanthakumar, Suntharalingam. Tue .
"Solvent extraction system for plutonium colloids and other oxide nano-particles". United States. https://www.osti.gov/servlets/purl/1133666.
@article{osti_1133666,
title = {Solvent extraction system for plutonium colloids and other oxide nano-particles},
author = {Soderholm, Lynda and Wilson, Richard E and Chiarizia, Renato and Skanthakumar, Suntharalingam},
abstractNote = {The invention provides a method for extracting plutonium from spent nuclear fuel, the method comprising supplying plutonium in a first aqueous phase; contacting the plutonium aqueous phase with a mixture of a dielectric and a moiety having a first acidity so as to allow the plutonium to substantially extract into the mixture; and contacting the extracted plutonium with second a aqueous phase, wherein the second aqueous phase has a second acidity higher than the first acidity, so as to allow the extracted plutonium to extract into the second aqueous phase. The invented method facilitates isolation of plutonium polymer without the formation of crud or unwanted emulsions.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jun 03 00:00:00 EDT 2014},
month = {Tue Jun 03 00:00:00 EDT 2014}
}
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