Separation of uranium from technetium in recovery of spent nucle

Details Separation of uranium from technetium in recovery of spent nucle Separation of uranium from technetium in recovery of spent nucle

1984-06-13

1985-07-09

Gron, Teddy S.

Chemistry of inorganic compounds

Treating mixture to obtain metal containing compound

Radioactive metal

423 2, 423 49, C01G 4300, C01G 5700

Patent

active

045281653

ABSTRACT:
A method for decontaminating uranium product from the Purex process comprises addition of hydrazine to the product uranyl nitrate stream from the Purex process, which contains hexavalent (UO.sub.2.sup.2+) uranium and heptavalent technetium (TcO.sub.4 -). Technetium in the product stream is reduced and then complexed by the addition of oxalic acid (H.sub.2 C.sub.2 O.sub.4), and the Tc-oxalate complex is readily separated from the uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.

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Campbell, M. H. "Extraction of Pertechnetate in a Purex Process", Hanford Atomic Products Operation, Richland, Washington, HW-69712, May 24, 1961.
Saraceno, A. J. "The Control of Technetium of the Portsmouth Gaseous Diffusion Plant", Goodyear Atomic Corp., Piketon, Ohio, GAT-2010, Nov. 1981.
Siddall, T. H., "Behavior of Technetium in the Purex Process", DuPont, At. En. Tech. Div., Savannah River Lab., M-3679, 22rd Ed., Rev. 1, Apr. 1959.

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