C - Chemistry – Metallurgy – 01 – G
Patent
C - Chemistry, Metallurgy
01
G
53/192
C01G 43/00 (2006.01) C09K 3/00 (2006.01) C22B 60/02 (2006.01) G21F 9/12 (2006.01)
Patent
CA 1239799
ABSTRACT OF THE DISCLOSURE A process for separating large amounts of uranium from small amounts of radioactive fission products, which are present in basic, aqueous carbonate containing solutions, by means of a basic, organic anion exchanger. Uranium values present as uranyl-carbonato complex in a basic, aqueous, carbonate containing solution can be separated from fission products of the group ruthenium, zirconium, niobium and lanthanide, and with a relatively high degree of decontamination as well. The aqueous solution is adjusted to a ratio of uranyl ion concentration to carbonate ion- or CO3--/HCO3- concentration of 1(UO2++) to 4.5(CO3--, or CO3--/HCO3-), or more, at a maximum U concentration of not more than 60 g/l. The adjusted solution is led over a basic anion exchanger made from a polyalkene matrix provided with a preponderant part tertiary and a minor part quaternary amino groups to adsorb fission products ions or fission products containing ions. The unadsorbed uranyl-carbonato complex is recovered in a decontaminated, preponderantly fission product free form by separating the uranium containing, remaining aqueous solution from the ion exchanger.
488036
Ali Sameh A.h.
Haag Jurgen
Fetherstonhaugh & Co.
Kernforschungszentrum Karlsruhe G.m.b.h.
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