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Flowsheets for the Validation of the Reference AmSEL System

Vanel, Vincent ; Wilden, Andreas; Modolo, Giuseppe; Geist, Andreas ORCID iD icon 1; Montuir, Marc; Guilbaud, P. [Hrsg.]
1 Institut für Nukleare Entsorgung (INE), Karlsruher Institut für Technologie (KIT)

Abstract:

Recycling americium (Am) from spent nuclear fuels is an important option considered for the future nuclear fuel cycle as americium is the main contributor to the long-term radiotoxicity and heat power of the ultimate waste. The
AmSEL flowsheet aims at recovering and purifying americium from a PUREX raffinate. This separation can be achieved by co-extracting lanthanide(III) (Ln) and actinide(III) cations (Am(III) and Cm(III)) into an organic phase containing the TODGA extractant (N,N,N',N'-tetraoctyl diglycolamide), and then stripping Am(III) selectively towards curium and lanthanides. The water-soluble ligand SO3-Ph-BTBP (6,6′-bis(5,6-dialkyl-1,2,4-triazin-3-yl)-2,2′-bipyridine) is used to selectively strip Am from the loaded organic phase. The objective of this work is to design a flowsheet for the Am stripping and Cm re-extraction steps to recover americium selectively from Cm and Ln, with TODGA as extractant and SO3-Ph-BTBP as complexing reagent. The test was implemented in August 2023 at FZ Jülich with trace amounts of americium and curium.


Verlagsausgabe §
DOI: 10.5445/IR/1000178604
Veröffentlicht am 03.02.2025
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Nukleare Entsorgung (INE)
Publikationstyp Zeitschriftenaufsatz
Publikationsjahr 2025
Sprache Englisch
Identifikator ISSN: 2100-014X
KITopen-ID: 1000178604
HGF-Programm 32.11.03 (POF IV, LK 01) Fundamental Scientific Aspects
Erschienen in EPJ Web of Conferences
Verlag EDP Sciences
Band 317
Seiten Article no: 01013
Vorab online veröffentlicht am 31.01.2025
Nachgewiesen in Scopus
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