SACSESS – the EURATOM FP7 project on actinide separation from spent nuclear fuels
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References
- 1. Bourg, S., Hill, C., Caravaca, C., Rhodes, C., Ekberg, C., Taylor, R., Geist, A., Modolo, G., Cassayre, L., Malmbeck, R., Harrison, M., de Angelis, G., Espartero, A., Bouvet, S., & Ouvrier, N. (2011). ACSEPT - Partitioning technologies and actinide science: Towards pilot facilities in Europe. Nucl. Eng. Des., 241, 3427-3435. DOI: 10.1016/j.nucengdes.2011.03.011.
- 2. Salvatores, M., & Palmiotti, G. (2011). Radioactive waste partitioning and transmutation within advanced fuel cycles: Achievements and challenges. Prog. Part. Nucl. Phys., 66, 144-166.
- 3. SACSESS report summary, http://cordis.europa.eu/result/rcn/158019_en.html.
- 4. Modolo, G., Wilden, A., Geist, A., Magnusson, D., & Malmbeck, R. (2012). A review of the demonstration of innovative solvent extraction processes for the recovery of trivalent minor actinides from PUREX raffinate. Radiochim. Acta, 100, 715-725. DOI: 10.1524/ract.2012.1962.
- 5. Wilden, A., Modolo, G., Schreinemachers, C., Sadowski, F., Lange, S., Sypula, M., Magnusson, D., Geist, A., Lewis, F. W., Harwood, L. M., & Hudson, M. J. (2013). Direct selective extraction of actinides(III) from PUREX raffi nate using a mixture of CyMe4BTBP and TODGA as 1-cycle SANEX solvent. Part III: Demonstration of a laboratory-scale counter-current centrifugal contactor process. Solvent Extr. Ion Exch., 31, 519-537. DOI: 10.1080/07366299.2013.775890.
- 6. Modolo, G., Asp, H., Schreinemachers, C., & Vijgen, H. (2007). Development of a TODGA based process for partitioning of actinides from a PUREX raffinate. Part I: Batch extraction optimization studies and stability tests. Solvent Extr. Ion Exch., 25, 703-721. DOI: 10.1080/07366290701634578.
- 7. Wilden, A., Modolo, G., Kaufholz, P., Sadowski, F., Lange, S., Sypula, M., Magnusson, D., Muellich, U., Geist, A., & Bosbach, D. (2015). Laboratory-scale counter-current centrifugal contactor demonstration of an innovative-SANEX process using a water soluble BTP. Solvent Extr. Ion Exch., 33, 91-108. DOI: 10.1080/07366299.2014.952532.
- 8. Carrott, M., Geist, A., Hérès, X., Lange, S., Malmbeck, R., Miguirditchian, M., Modolo, G., Wilden, A., & Taylor, R. (2015). Distribution of plutonium, americium and interfering fi ssion products between nitric acid and a mixed organic phase of TODGA and DMDOHEMA in kerosene, and implications for the design of the “EURO-GANEX” process. Hydrometallurgy, 152, 139-148.
- 9. Poinssot, C., Rostaing, C., Baron, P., Warin, D., & Boullis, B. (2012). Main results of the French program on partitioning of minor actinides, a signifi cant improvement towards nuclear waste reduction. Procedia Chem., 7, 358-366. DOI: 10.1016/j. proche.2012.10.056.
- 10. Rostaing, C., Poinssot, C., Warin, D., Baron, P., & Lorrain, B. (2012). Development and validation of the EXAm separation process for single Am recycling. Procedia Chem., 7, 367-373.
- 11. Modolo, G., Kluxen, P., & Geist, A. (2010) Demonstration of the LUCA process for the separation of americium(III) from curium(III), californium(III), and lanthanides(III) in acidic solution using a synergistic mixture of bis(chlorophenyl)dithiophosphinic acid and tris(2-ethylhexyl)phosphate. Radiochim. Acta, 98, 193-201. DOI: 10.1524/ract.2010.1708.
- 12. Bollesteros, M. -J., Calor, J. -N., Costenoble, S., Montuir, M., Pacary, V., Sorel, C., Burdet, F., Espinoux, D., Hérès, X., & Eysseric, C. (2012). Implementation of americium separation from a PUREX raffinate. Procedia Chem., 7, 178-183.
- 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.
- 15. Bryantsev, V. S., & Hay, B. P. (2015). Theoretical prediction of Am(III)/Eu(III) selectivity to aid the design of actinide-lanthanide separation agents. Dalton Trans., 44(17), 7935-7942. DOI: 10.1039/c4dt03275f.
- 16. Mincher, B. J., Elias, G., Martin, L. R., & Mezyk, S. P. (2009). Radiation chemistry and the nuclear fuel cycle. J. Radioanal. Nucl. Chem., 282, 645-649.
- 17. Inoue, T. (2002). Actinide recycling by pyro-process with metal fuel FBR for future nuclear fuel cycle system. Prog. Nucl. Energy, 40, 547-554.
- 18. Koyama, T., Sakamura, Y., Iizuka, M., Kato, T., Murakami, T., & Glatz, J. -P. (2012). Development of pyro-processing fuel-cycle technology for closing actinide cycle. Procedia Chem., 7, 772-778.
- 19. Soucek, P., Malmbeck, R., Nourry, C., & Glatz, J. -P. (2011). Pyrochemical reprocessing of spent fuel by electrochemical techniques using solid aluminium cathodes. Energy Procedia, 7, 396-404.
- 20. Chmielewski, A. G. (2008). Nuclear fi ssile fuels worldwide reserves. Nukleonika, 53(Suppl. 2), S11-S14.
- 21. http://asgardproject.eu/
- 22. www.talisman-project.eu
- 23. http://cinch-project.eu/
- 24. John, J., Lehto, J., Koivula, T., & Omtvedt, J. P. (2015). Cooperation in education and training in nuclear- and radiochemistry in Europe. J. Radioanal. Nucl. Chem., 304, 459-466.
Language: English
Page range: 809 - 814
Submitted on: Oct 9, 2015
Accepted on: Oct 9, 2015
Published on: Dec 30, 2015
Published by: Institute of Nuclear Chemistry and Technology
In partnership with: Paradigm Publishing Services
Publication frequency: 4 issues per year
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© 2015 Stéphane Bourg, Andreas Geist, Jerzy Narbutt, published by Institute of Nuclear Chemistry and Technology
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.