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Title: 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 Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1133666
Patent Number(s):
8,741,237
Application Number:
12/758,106
Assignee:
U.S. Department of Energy (Washington, DC)
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 = {2014},
month = {6}
}

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Works referenced in this record:

Extraction of plutonium from sulphuric acid by TOA in toluene
journal, September 1976

  • Južnič, K.; Fedina, Š.; Senegačnik, M.
  • Journal of Radioanalytical Chemistry, Vol. 30, Issue 2
  • DOI: 10.1007/BF02516975

Liquid−Liquid Equilibria of Aqueous Acetic Acid Derivatives with Trioctylamine and Select Organic Diluents
journal, September 2003

  • Li, Zhenyu; Qin, Wei; Dai, Youyuan
  • Journal of Chemical & Engineering Data, Vol. 48, Issue 5
  • DOI: 10.1021/je025628z