Anion Exchange Recovery of Plutonium From Reduction Residues

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An anion exchange process was demonstrated for the recovery of Pu from waste produced in the reduction of Pu salts to the metal. Pu in a highiy salted 6M nitric acid solution, derived from the dissolution of slag and crucible waste, was separated from impurities by absorbing the Pu(IV) nitrate complex on the anion exchange resin and subsequentiy eluting with dilute nitric acid. A flowsheet for plant operation is presented. (auth)

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Russell, E. R. February 1, 1960.

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An anion exchange process was demonstrated for the recovery of Pu from waste produced in the reduction of Pu salts to the metal. Pu in a highiy salted 6M nitric acid solution, derived from the dissolution of slag and crucible waste, was separated from impurities by absorbing the Pu(IV) nitrate complex on the anion exchange resin and subsequentiy eluting with dilute nitric acid. A flowsheet for plant operation is presented. (auth)

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Other Information: Orig. Receipt Date: 31-DEC-63

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  • February 1, 1960

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  • Oct. 18, 2017, 7:39 a.m.

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  • Nov. 22, 2024, 11:26 p.m.

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Russell, E. R. Anion Exchange Recovery of Plutonium From Reduction Residues, report, February 1, 1960; Aiken, South Carolina. (https://digital.library.unt.edu/ark:/67531/metadc1028560/: accessed April 17, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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