Glutarimidedioxime: A Complexing and Reducing Reagent for Plutonium Recovery from Spent Nuclear Fuel Reprocessing.

Autor: Xian L; Radiochemistry Department, China Institute of Atomic Energy, P. O. Box 275-26, Beijing, 102413, China., Tian G; Radiochemistry Department, China Institute of Atomic Energy, P. O. Box 275-26, Beijing, 102413, China. gtian@ciae.ac.cn.; Chemical Sciences Division, Lawrence Berkeley National Laboratory, Berkeley, CA, 94720, USA. gtian@ciae.ac.cn., Beavers CM; Advanced Light Source, Lawrence Berkeley National Laboratory, Berkeley, CA, 94720, USA., Teat SJ; Advanced Light Source, Lawrence Berkeley National Laboratory, Berkeley, CA, 94720, USA. steat@lbl.gov., Shuh DK; Chemical Sciences Division, Lawrence Berkeley National Laboratory, Berkeley, CA, 94720, USA. dkshuh@lbl.gov.
Jazyk: angličtina
Zdroj: Angewandte Chemie (International ed. in English) [Angew Chem Int Ed Engl] 2016 Apr 04; Vol. 55 (15), pp. 4671-3. Date of Electronic Publication: 2016 Mar 11.
DOI: 10.1002/anie.201510712
Abstrakt: Efficient separation processes for recovering uranium and plutonium from spent nuclear fuel are essential to the development of advanced nuclear fuel cycles. The performance characteristics of a new salt-free complexing and reducing reagent, glutarimidedioxime (H2A), are reported for recovering plutonium in a PUREX process. With a phase ratio of organic to aqueous of up to 10:1, plutonium can be effectively stripped from 30% tributyl phosphate (TBP) in kerosene into 1 M HNO3 with H2A. The complexation-reduction mechanism is illustrated with the combination of UV/Vis absorption spectra and the crystal structure of a Pu(IV) complex with the reagent. The fast stripping rate and the high efficiency for stripping Pu(IV), through the complexation-reduction mechanism, is suitable for use in centrifugal contactors with very short contact/resident times, thereby offering significant advantages over conventional processes.
(© 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.)
Databáze: MEDLINE
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