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Title: Solvent extraction system for plutonium colloids and other oxide nano-particles

Patent ·
OSTI ID:1133666
; ; ;

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.

Research Organization:
Argonne National Laboratory (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC02-06CH11357
Assignee:
U.S. Department of Energy (Washington, DC)
Patent Number(s):
8,741,237
Application Number:
12/758,106
OSTI ID:
1133666
Country of Publication:
United States
Language:
English

References (5)

Process for the extraction of uranium (VI) and/or plutonium (IV) present in an aqueous solution by means of N,N-dialkylamides patent September 1988
Process for Reprocessing a Spent Nuclear Fuel and of Preparing a Mixed Uranium-Plutonium Oxide patent-application December 2007
Method of Removing the Polymer Encapsulating a Nuclear Fuel Pellet patent-application June 2011
Extraction of plutonium from sulphuric acid by TOA in toluene journal September 1976
Liquid−Liquid Equilibria of Aqueous Acetic Acid Derivatives with Trioctylamine and Select Organic Diluents journal September 2003

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