Process for the separation of large amounts of uranium from smal

Details Process for the separation of large amounts of uranium from smal Process for the separation of large amounts of uranium from smal

1985-08-05

1987-09-29

Miller, Edward A.

Compositions

Radioactive compositions

423 2, 423 7, 423 17, C01G 4300, C22B 6002, C09K 300

Patent

active

046967680

ABSTRACT:
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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patent: 2811412 (1957-10-01), Poirier
patent: 2864667 (1958-12-01), Bailes et al.
patent: 3155455 (1964-11-01), Hart
patent: 3835044 (1974-09-01), Schulz
patent: 3922231 (1975-11-01), Carlin et al.
patent: 4280985 (1981-07-01), Yon
patent: 4460547 (1984-07-01), Sameh et al.

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