Am(VI) Centrifugal Contactor Hot Testing

Technical Report · Thu Aug 24 04:00:00 EDT 2017

DOI:https://doi.org/10.2172/1408744· OSTI ID:1408744

Mincher, Bruce J. ^[1]; Tillotson, Richard D. ^[1]; Schmitt, Nicholas C. ^[1]; Cedar, Joakim S. ^[1]

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1. Idaho National Lab. (INL), Idaho Falls, ID (United States)

A series of hot tests was performed with a goal of establishing flowsheet conditions for the separation of Am(VI) from the lanthanides. All experiments were performed using 2-cm, acrylic 3D-printed centrifugal contactors. Americium(VI) and Ce(IV) extraction was performed with 1 M DEHBA/dodecane, following oxidation with 60 mg mL^-1 sodium bismuthate. Although filtering residual bismuthate prior to feeding the aqueous phase to the extraction contactor has previously been successful, a newly acquired lot of filters exhibited reducing activity toward Am and could not be used in testing. Therefore, bismuthate was removed by settling. Longer settling times resulted in lower D_Am, probably because of the decreased amount of holding oxidant in the feed. However, a compromise time allowed for efficient Am(VI) solvent extraction (D_Am ~ 2.5, % E ~ 70) Solids accumulated on the extraction contactor rotor, however; and filtering will be necessary in a process. Selective stripping was attempted by allowing the loaded solvent to stand for ~5 minutes, during which time it was expected that Am would reduce and be selectively stripped from Ce. However, both metals reduced and were co-stripped into 6.5 M HNO₃. Successful recycle of the used organic phase was demonstrated.

• Research Organization: Idaho National Laboratory, Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1408744
• Report Number(s): INL/EXT--17-43049
• Country of Publication: United States
• Language: English

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