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| Hauptseite > Publikationsdatenbank > Process development studies towards the selective separation of Am(III) in the AmSEL process |
| Hauptseite > Publikationsdatenbank > Process development studies towards the selective separation of Am(III) in the AmSEL process |
| Talk (non-conference) (Other) | FZJ-2023-02409 |
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2023
Abstract: The recycling of Americium is considered a viable option for future extended nuclear fuel cycles. How-ever, the separation of Am(III) from Cm(III) and trivalent lanthanides contained in used nuclear fuel is still one of the most difficult challenges in element separations, and only few examples of selective Am(III) separation exist to date (e.g., EXAm).[1] Within the course of recent European collaborative pro-jects, a chemical system was developed making use of the opposite selectivity of the well-known TODGA (N,N,N',N'-tetraoctyldiglycolamide, Figure 1) extractant and the hydrophilic sulphonated SO3-Ph-BTBP (sodium 3,3’,3’’,3’’’-([2,2’-bipyridine]-6,6’-diylbis(1,2,4-triazine-3,5,6-triyl))-tetrabenzenesul-fonate, Figure 1). This so-called AmSEL process was developed to selectively strip Am(III) from a loaded TODGA solvent containing Am, Cm and trivalent lanthanides.[2] Stripping kinetics were measured in single centrifugal contactors and a flow-sheet is currently under development using the French PAREX code.[3] This presentation will highlight the development of the AmSEL process and discuss the current flow-sheet. A process demonstration in our 16-stage centrifugal contactor setup is planned soon.Funding for this research was provided by the European Commission through the GEN IV Integrated Oxide Fuels Recycling Strategies (GENIORS) project, grant agreement number 730227 and the Parti-tioning And Transmuter Research Initiative in a Collaborative Innovation Action (PATRICIA) project, grant agreement number 945077.
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