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Gamma radiolytic stability of the novel modified diglycolamide 2,2′-oxybis(N,N-didecylpropanamide) (mTDDGA) for grouped actinide extraction

Reprocessing of spent nuclear fuel aims at improving resource efficiency and reducing its radiotoxicity and heat production in the long term. The necessary separation of certain metal ions from the spent fuel solutions can be achieved using different solvent extraction processes. For the scenario of...

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Detalles Bibliográficos
Autores principales: Verlinden, Bart, Van Hecke, Karen, Wilden, Andreas, Hupert, Michelle, Santiago-Schübel, Beatrix, Egberink, Richard J. M., Verboom, Willem, Kowalski, Piotr M., Modolo, Giuseppe, Verwerft, Marc, Binnemans, Koen, Cardinaels, Thomas
Formato: Online Artículo Texto
Lenguaje:English
Publicado: The Royal Society of Chemistry 2022
Materias:
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9036757/
https://www.ncbi.nlm.nih.gov/pubmed/35480374
http://dx.doi.org/10.1039/d1ra08761d