Chemistry of inorganic compounds – Treating mixture to obtain metal containing compound – Radioactive metal
Patent
1983-08-31
1984-04-17
Miller, Edward A.
Chemistry of inorganic compounds
Treating mixture to obtain metal containing compound
Radioactive metal
423 2, C01G 4300, C01G 5700
Patent
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.
REFERENCES:
patent: 2982601 (1961-05-01), Wilson
patent: 3374068 (1968-03-01), Erlandson et al.
patent: 3808320 (1974-04-01), Kaiser et al.
patent: 3827986 (1974-08-01), Charlton et al.
patent: 4092265 (1978-05-01), Longo et al.
patent: 4116863 (1978-09-01), Berton et al.
patent: 4162231 (1979-07-01), Horwitz et al.
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.
McTaggart Donald R.
Pruett David J.
Esposito Michael F.
Grant Edwin D.
Hamel Stephen D.
Miller Edward A.
The United States of America as represented by the United States
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