Process Evaluations For Uranium Recovery From Scrap Material

The Minerals, Metals and Materials Society
B. R. Westphal
Organization:
The Minerals, Metals and Materials Society
Pages:
9
File Size:
426 KB
Publication Date:
Jan 1, 1992

Abstract

The Integral Fast Reactor (IFR) concept being developed by Argonne National Laboratory is based on the pyrometallurgical processing of spent nuclear metallic fuel with subsequent fabrication into new reactor fuel by an injection casting process. During fabrication, a dilute scrap stream containing uranium alloy fines and broken quartz (Vycor) molds is produced. Waste characterization of this stream, developed by using present operating data and chemical analysis, was used to evaluate different uranium recovery methods and possible process variations for the return of the recovered metal. Two methods, comminution with size separation and electrostatic separation, have been tested and can successfully recover over 94% of the metal. Recycling the recovered metal to the injection casting process was evaluated for the different economic and process impacts. The physical waste parameters and the important separation process variables are discussed relative to their effects on the viability of recycling the material. A discussion of the criteria that is being used to establish the acceptable operating limits is also presented.
Citation

APA: B. R. Westphal  (1992)  Process Evaluations For Uranium Recovery From Scrap Material

MLA: B. R. Westphal Process Evaluations For Uranium Recovery From Scrap Material. The Minerals, Metals and Materials Society, 1992.

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