Kernforschungszentrum Karlsruhe Gmbh

Sameh A Ali

Werner Faubel

Juergen Haag

The invention relates to a process for continuous or almost continuous separation of cesium ions from aqueous solutions having high concentrations of sodium and/or potassium ions by ion exchange with ammonium molybdophosphate (AMP). A quantitative cesium separation from aqueous solutions which are high in salts, especially from highly radioactive solutions which are strongly nitric and contain nitrate, is achieved, without having to consider bleeding of the AMP and/or undesirable local overheating in the exchanger.

Process for separation of cesium ions from aqueous solutions

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 uranykl-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 CO.sub.3.sup.-- /HCO.sub.3.sup.- concentration of 1(UO.sub.2.sup.++) to 4.5(CO.sub.3.sup.--, or CO.sub.3.sup.-- /HCO.sub.3.sup.-), 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.

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Ettlingen, Germany

Sameh A Ali