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2015 | 60 | 4 | 809-814

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SACSESS – the EURATOM FP7 project on actinide separation from spent nuclear fuels


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Recycling of actinides by their separation from spent nuclear fuel, followed by transmutation in fast neutron reactors of Generation IV, is considered the most promising strategy for nuclear waste management. Closing the fuel cycle and burning long-lived actinides allows optimizing the use of natural resources and minimizing the long-term hazard of high-level nuclear waste. Moreover, improving the safety and sustainability of nuclear power worldwide. This paper presents the activities striving to meet these challenges, carried out under the Euratom FP7 collaborative project SACSESS (Safety of Actinide Separation Processes). Emphasis is put on the safety issues of fuel reprocessing and waste storage. Two types of actinide separation processes, hydrometallurgical and pyrometallurgical, are considered, as well as related aspects of material studies, process modeling and the radiolytic stability of solvent extraction systems. Education and training of young researchers in nuclear chemistry is of particular importance for further development of this field.










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1 - 12 - 2015
30 - 12 - 2015
9 - 10 - 2015
9 - 10 - 2015


  • Commissariat à l'Énergie Atomique et aux Énergies Alternatives (CEA), Radiochemistry and Process Department, Marcoule, France
  • Karlsruhe Institute of Technology (KIT), Postfach 3640, D-76021, Karlsruhe, Germany
  • Institute of Nuclear Chemistry and Technology, 16 Dorodna Str., 03-195 Warsaw, Poland


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  • 13. Chapron, S., Marie, C., Arrachart, G., Miguirditchian, M., & Pellet-Rostaing, S. (2015). New insight into the americium/curium separation by solvent extraction using diglycolamides. Solvent Extr. Ion Exch., 33(3), 236-248.
  • 14. Narbutt, J., Wodyński, A., & Pecul, M. (2015). The selectivity of diglycolamide (TODGA) and bis-triazine--bipyridine (BTBP) ligands in actinide/ lanthanide complexation and solvent extraction separation - a theoretical approach. Dalton Trans., 44(6), 2657-2666. DOI: 10.1039/c4dt02657h.[WoS][Crossref]
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