Separation of uranium from technetium in recovery of spent nucle

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

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423 2, C01G 4300, C01G 5700

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active

044434138

ABSTRACT:
Uranium and technetium in the product stream of the Purex process for recovery of uranium in spent nuclear fuel are separated by (1) contacting the aqueous Purex product stream with hydrazine to reduce Tc.sup.+7 therein to a reduced species, and (2) contacting said aqueous stream with an organic phase containing tributyl phosphate and an organic diluent to extract uranium from said aqueous stream into said organic phase.

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Campbell "Extraction of Pertechnetate in a Purex Process", HW-69712, Hanford Atomic Prod. Op. (May 24, 1981) Richland, Wa.
Saracceno, "The Control of Technetium at the Portsmouth Gaseous Diffusion Plant", GAT-2010, Goodyear Atomic Corp. (Nov. 1981) Piketon, Ohio.
Siddall, "Behavior of Technetium in the Purex Process", M-3679, 22nd Ed., Rev. 1, E. I. Du Pont de Nemours & Co., At. En. Div. Techn. Div. (Apr. 1959) Savannah R.V. Lab.

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