Solvent Extraction of Uranium from Sulfuric Acid Eluates
Author : Henry G. Petrow
Publisher :
Page : 40 pages
File Size : 49,72 MB
Release : 1958
Category : Solvent extraction
ISBN :
Author : Henry G. Petrow
Publisher :
Page : 40 pages
File Size : 49,72 MB
Release : 1958
Category : Solvent extraction
ISBN :
Author :
Publisher :
Page : pages
File Size : 26,52 MB
Release : 1956
Category :
ISBN :
Author : D'Arcy R. George
Publisher :
Page : 18 pages
File Size : 47,90 MB
Release : 1969
Category : Ion exchange
ISBN :
Author : Al Preuss
Publisher :
Page : 40 pages
File Size : 37,45 MB
Release : 1955
Category : Amines
ISBN :
Fifty oil soluble amines were screened for possible use as extractants for uranium from sulfuric acid solutions. The most promising of these were studied further to obtain the optimum conditions for operation of such a process. Kerosene was used as the diluent.
Author : W. D. Charles
Publisher :
Page : 88 pages
File Size : 29,41 MB
Release : 1957
Category : Solvent extraction
ISBN :
Author : R. Simard
Publisher : R. Duhamel
Page : 10 pages
File Size : 38,69 MB
Release : 1961
Category : Leaching
ISBN :
Author :
Publisher :
Page : 66 pages
File Size : 28,2 MB
Release : 1959
Category : Chattanooga Shale
ISBN :
Author : OECD Nuclear Energy Agency
Publisher : Paris, France : Organisation for Economic Co-operation and Development ; [Washington, D.C. : OECD Publications and Information Center
Page : 286 pages
File Size : 31,80 MB
Release : 1983
Category : Ore-dressing
ISBN :
Author :
Publisher :
Page : pages
File Size : 37,13 MB
Release : 1965
Category :
ISBN :
The chemistry of the Bufflex solvent-extraction process is described. Uranium is extracted by a tertiary amine solvent, from which the impurities are removed by means of dilute ammonia, and the uranium is stripped by an ammonium sulphate strip. In the pilot plant, these processes are carried out in mixer-settlers. Details of pumps, flow controllers, and materials of construction are given. The operation of the extraction, scrub, strip, precipitation and thickening, and regeneration sections is described. Comparative tests on the elution of ion-exchange resin with 10 per cent sulphuric acid, and with nitrate, are described. The results of resin analyses and plant tests are given. A breakdown of the costs of reagents in the Bufflex process, compared with the conventional process, is given. It is concluded that a solvent-extraction process treating the sulphuric acid eluate from ion-exchange columns is technically feasible. As regards the resin itself, elution with 10 per cent sulphuric acid is satisfactory. There is more polythionate build-up than with nitrate elution, and the capacity of the resin is slightly lower, but the difference is small. The operating cost of the Bufflex process is cheaper by at least 5 cents per pound of U3O8 produced. The product satisfies the most stringent specification for nuclear-grade uranium, except as regards cobalt, molybdenum, silicon, and hafnium.
Author : R. E. Berning
Publisher :
Page : 134 pages
File Size : 46,45 MB
Release : 1953
Category : Phosphoric acid
ISBN :
A solvent extraction process for the recovery of Uranium from Phosphoric Acid is described. The process steps which include reduction, extraction, unloading and acid clean-up are presented in detail. An estimated process cost is also presented.