The Removal of Uranium from Acidic Media Using lon-Exchange and/or Extraction Chromatography (063e3763-56bb-45f1-9bf2-d18289035e8c)

The Minerals, Metals and Materials Society
John R. FitzPatrick Brad S. Schake Jennifer Murphy Karol Holmes Mike H. West
Organization:
The Minerals, Metals and Materials Society
Pages:
16
File Size:
699 KB
Publication Date:
Jan 1, 1996

Abstract

"The separation and purification of uranium from either nitric acid or hydrochloric acid media can be accomplished by using either solvent extraction or ion-exchange. Over the past two years at Los Alamos, emerging programs are focused on recapturing the expertise required to do limited, small-quantity processing of enriched uranium. During this period of time, we have been investigating ion-exchange as a method for extraction/purification of uranium from acidic media. In addition, waste stream polishing is associated with this effort in order to achieve more complete removal of the uranium prior to recycle of the acid. Extraction chromatography has been demonstrated to further polish the uranium from both nitric and hydrochloric acid media thus allowing for a more complete recovery of the actinide material and creation of less waste during the processing steps.We will discuss contact experiments for evaluation of eleven different resins for uranium removal from nitric acid, the evaluation (again by contact experiments) of uranium elution from the ion-exchange media by various chemicals, and small-scale experiments for the removal of 235U from nitric acid. Larger-scale (1 DO-gram) flow experiments, using depleted uranium, were done after the small-scale evaluation of the selected resin. A discussion is also included concerning the shortcomings of the contact experiments and how the flow experiments were modified in order to overcome these problems. We will also discuss the application of ion-exchange for some specific process needs at Los Alamos.Contact experiments were used to evaluate some commercially available solvent-impregnated resins in addition to evaluation of several resins of this type synthesized in our laboratory. These experiments involved both nitric and hydrochloric acid media. The data from these experiments will be used to determine the column size and amount of resin required to polish the waste stream produced by the ion-exchange process described above. Small-scale flow experiments will be described and data given on the mass balances achieved using this two step process.Future work for evaluation of new ion-exchange and solvent-impregnated resins as well as the search for new eluants will be discussed. Other future experiments for both processes, including large-scale experiments, will be discussed in detail."
Citation

APA: John R. FitzPatrick Brad S. Schake Jennifer Murphy Karol Holmes Mike H. West  (1996)  The Removal of Uranium from Acidic Media Using lon-Exchange and/or Extraction Chromatography (063e3763-56bb-45f1-9bf2-d18289035e8c)

MLA: John R. FitzPatrick Brad S. Schake Jennifer Murphy Karol Holmes Mike H. West The Removal of Uranium from Acidic Media Using lon-Exchange and/or Extraction Chromatography (063e3763-56bb-45f1-9bf2-d18289035e8c). The Minerals, Metals and Materials Society, 1996.

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