Process for the recovery of uranium values in an extractive repr

Chemistry of inorganic compounds – Treating mixture to obtain metal containing compound – Radioactive metal

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423 2, 423 17, C01G 4300

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active

047403594

ABSTRACT:
An organic extraction phase, containing fission materials uranium and plutonium, as well as a minor amount of fission- and corrosion-products, from an extraction step or from a purification step of a nuclear fuel reprocessing process is treated with an aqueous, basic, carbonate ion containing solution, whereby the fission materials and at least a part of the fission- and corrosion-products are stripped into the aqueous phase and the uranium is present in the form of uranium-carbonato-complex. The organic phase is then separated from the aqueous phase. Plutonium is then removed from the separated aqueous phase. The remaining aqueous solution containing the uranium-carbonato-complex and a small residual amount (C) of fission products 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.-- /HNO.sub.3.sup.-), respectively, or more, at a maximum U-concentration of not more than 6- g/l. The adjusted solution is then 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 product ions or fission products containing ions. The unadsorbed uranyl-carbonato complex which is now decontaminated, and preponderantly fission product free is recovered by separating the uranium containing, remaining aqueous solution from the ion exchanger.

REFERENCES:
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patent: 3155455 (1964-11-01), Hart
patent: 3835044 (1974-09-01), Schulz
patent: 3864667 (1958-12-01), Bailes et al.
patent: 3922231 (1975-11-01), Carlin et al.
patent: 4280985 (1981-07-01), Yan
patent: 4460547 (1984-07-01), Sameh et al.

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