Skip to main content
Have a personal or library account? Click to login
Reprocessability of molybdenum and magnesia based inert matrix fuels Cover

Reprocessability of molybdenum and magnesia based inert matrix fuels

Nukleonika
Volume 60 (2015): Issue 4 (December 2015)
By: ,  ,  ,  ,   and    
Open Access
|Dec 2015
References

References

  1. 1. Pillon, S. (2012). Actinide-bearing fuels and transmutation targets. In R. J. M. Konings (Ed.), Comprehensive nuclear materials (Vol. 3, pp. 109-141). Oxford: Elsevier.
    Search in Google Scholar
  2. 2. 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.
    Open DOISearch in Google Scholar
  3. 3. Montel, J. -M. (2011). Minerals and design of new waste forms for conditioning nuclear waste. C. R. Geosci., 343, 230-236. DOI: 10.1016/j. crte.2010.11.006.
    Search in Google Scholar
  4. 4. Lamontagne, J., Béjaoui, S., Hanifi , K., Valot, C., & Loubet, L. (2011). Swelling under irradiation of MgO pellets containing americium oxide: The ECRIX-H irradiation experiment. J. Nucl. Mater., 413, 137-144. DOI: 10.1016/j.jnucmat.2011.04.013.
    Open DOISearch in Google Scholar
  5. 5. D’Agata, E., Klaassen, F., Sciolla, C., Fernandes- -Carretero, A., & Bonnerot, J. M. (2009). Helios: The new design of the irradiation of U-free fuels for americium transmutation. In Proceedings of the Global, 6-11 September 2009 (pp. 2006-2015). Paris, France.
    Search in Google Scholar
  6. 6. Delage, F., Belin, R., Chen, X. -N., D’Agata, E., Klaassen, F., Knol, S., Maschek, W., Ottaviani, J. P., Rineiski, A., Sobolev, V., Somers, J., Staicu, D., Thetford, R., Wallenius, J., & Wernli, B. (2010). Minor actinide transmutation in an accelerator-driven system prototype: Results from fuel developments within the European programme EUROTRANS. In Proceedings of the Actinide and Fission Product Partitioning and Transmutation - Eleventh Information Exchange Meeting, 1-4 November 2010 (pp. 177-186). San Francisco.
    Search in Google Scholar
  7. 7. Haas, D., Fernandez, A., Staicu, D., Somers, J., Maschek, W., Liu, P., & Chen, X. (2008). CERMET fuel behavior and properties in ADS reactors. Energy Conv. Manag., 49, 1928-1933. DOI: 10.1016/j.enconman. 2007.12.027.
    Search in Google Scholar
  8. 8. Ekberg, C., deVisser-Tynova, E., Retegan, T., Sarsfi eld, M., & Wallenius, J. (2014). ASGARD. In Proceedings of the Sustainable Nuclear Energy Conference SNEC, 9-11 April 2014. Manchester.
    Search in Google Scholar
  9. 9. Ouvrier, N., & Boussier, H. (2012). Recycling of MgO, Mo & ZrO2 based actinide-bearing matrices: Assessment of reprocessing feasibility & waste production. Procedia Chem., 7, 322-327. DOI: 10.1016/j. proche.2012.10.051.
    Search in Google Scholar
  10. 10. Loveland, W. D., Morrissey, D. J., & Seaborg, G. T. (2006). Modern nuclear chemistry. New York, NY: Wiley.
    Search in Google Scholar
  11. 11. Taylor, R., Bourg, S., Glatz, J. -P., Modolo, G. (2015). Developement of actinide separation processes for future nuclear fuel cycles in Europe. Nucl. Future, 11(4), 38-43.
    Search in Google Scholar
  12. 12. Courson, O., Lebrun, M., Malmbeck, R., Pagliosa, G., Romer, K., Satmark, B., & Glatz, J. -P. (2000). Partitioning of minor actinides from HLLW using the DIAMEX process. Part 1 - Demonstration of extraction performances and hydraulic behaviour of the solvent in a continuous process. Radiochim. Acta, 88, 857-863. DOI: 10.1524/ract.2000.88.12.857.
    Open DOISearch in Google Scholar
  13. 13. Serrano-Purroy, D., Christiansen, B., Glatz, J. -P., Malmbeck, R., & Modolo, G. (2005). Towards a DIAMEX process using high active concentrate. Production of genuine solutions. Radiochim. Acta, 93, 357-361. DOI: 10.1524/ract.93.6.357.65645.
    Open DOISearch in Google Scholar
  14. 14. Serrano-Purroy, D., Baron, P., Christiansen, B., Malmbeck, R., Sorel, C., & Glatz, J. -P. (2005). Recovery of minor actinides from HLLW using the DIAMEX process. Radiochim. Acta, 93, 351-355. DOI: 10.1524/ ract.93.6.351.65642.
    Open DOISearch in Google Scholar
  15. 15. Baron, P., Hérès, X., Lecomte, M., & Masson, M. (2001). Separation of the minor actinides: the DIAMEX-SANEX concept. In Proceedings of the International Conference on Future Nuclear Systems, GLOBAL’01, 9-13 September 2001. Paris, France.
    Search in Google Scholar
  16. 16. Sasaki, Y., & Choppin, G. R. (1996). Solvent extraction of Eu, Th, U, Np and Am with N,N’-dimethyl- N,N’-dihexyl-3-oxapentanediamide and its analogous compounds. Anal. Sci., 12, 225-230. DOI: 10.2116/ analsci.12.225.
    Open DOISearch in Google Scholar
  17. 17. Sasaki, Y., & Choppin, G. R. (1998). Extraction of Np(V) by N,N'-dimethyl-N,N'-dihexyl-3-oxapentane- -diamide. Radiochim. Acta, 80, 85-88. DOI: 10.1524/ ract.1998.80.2.85.
    Open DOISearch in Google Scholar
  18. 18. Sasaki, Y., Sugo, Y., Suzuki, S., & Tachimori, S. (2001). The novel extractants, diglycolamides, for the extraction of lanthanides and actinides in HNO3-ndodecane system. Solvent Extr. Ion Exch., 19, 91-103. DOI: 10.1081/sei-100001376.
    Open DOISearch in Google Scholar
  19. 19. Modolo, G., Vijgen, H., Schreinemachers, C., Baron, P., & Dinh, B. (2003). TODGA process developement for partitioning of actinides(III) from PUREX raffinate. In Proceedings of the GLOBAL, 16-20 November 2003 (pp. 1926-1930). New Orleans, Louisiana, USA.
    Search in Google Scholar
  20. 20. Geist, A., & Modolo, G. (2009). TODGA process development: an improved solvent formulation. In Proceedings of the GLOBAL (The Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives), 6-11 September 2009 (pp. 1022-1026, paper 9193). Paris, France.
    Search in Google Scholar
  21. 21. Modolo, G., Asp, H., Schreinemachers, C., & Vijgen, H. (2007). Development of a TODGA based process for partitioning of actinides from a PUREX raffi nate Part I: Batch extraction optimization studies and stability tests. Solvent Extr. Ion Exch., 25, 703-721. DOI: 10.1080/07366290701634578.
    Open DOISearch in Google Scholar
  22. 22. Magnusson, D., Christiansen, B., Glatz, J. P., Malmbeck, R., Modolo, G., Serrano-Purroy, D., & Sorel, C. (2009). Demonstration of a TODGA based extraction process for the partitioning of minor actinides from a PUREX raffi nate. Solvent Extr. Ion Exch., 27, 26-35, DOI: 10.1080/07366290802544726.
    Open DOISearch in Google Scholar
  23. 23. Fukasawa, T., & Ozawa, Y. (1986). Relationship between dissolution rate of uranium dioxide pellets in nitric acid solutions and their porosity. J. Radioanal. Nucl. Chem. Lett., 106, 345-356. DOI: 10.1007/ BF02163667.
    Open DOISearch in Google Scholar
  24. 24. Ryan, J. L., Bray, L. A., Wheelwright, E. J., & Bryan, G. H. (1990). Catalyzed electrolytic plutonium oxide dissolution (CEPOD): The past seventeen years and future potential. United States: American Chemical Society.
    Search in Google Scholar
  25. 25. Uriarte, A. L., & Rainey, R. H. (1965). Dissolution of high-density UO2, PuO2, and UO2-PuO2 pellets in inorganic acids. Commission, U.S.A.E., Oak Ridge, Tennessee: Oak Ridge National Laboratory. (ORNL-3695).
    Open DOISearch in Google Scholar
  26. 26. Inoue, A. (1988). Enhanced dissolution of PuO2 in nitric acid using uranium(IV). J. Chem. Soc. Faraday Trans., 84, 1195-1197. DOI: 10.1039/F19888401195.
    Open DOISearch in Google Scholar
  27. 27. Fedorockova, A., & Raschman, P. (2008). Effects of pH and acid anions on the dissolution kinetics of MgO. Chem. Eng. J., 143, 265-272. DOI: 10.1016/j. cej.2008.04.029.
    Search in Google Scholar
  28. 28. Jordan, G., & Rammensee, W. (1996). Dissolution rates and activation energy for dissolution of brucite (001): A new method based on the microtopography of crystal surfaces. Geochim. Cosmochim. Acta, 60, 5055-5062. DOI: 10.1016/S0016-7037(96)00309-2.
    Open DOISearch in Google Scholar
  29. 29. Lüttge, A., Arvidson, R. S., & Fischer, C. (2013). A stochastic treatment of crystal dissolution kinetics. Elements, 9, 183-188. DOI: 10.2113/gselements. 9.3.183.
    Search in Google Scholar
  30. 30. Finkeldei, S., Brandt, F., Rozov, K., Bukaemskiy, A. A., Neumeier, S., & Bosbach, D. (2014). Dissolution of ZrO2 based pyrochlores in the acid pH range: A macroscopic and electron microscopy study. Appl. Geochem., 49, 31-41. DOI: 10.1016/j.apgeochem. 2014.06.014.
    Search in Google Scholar
  31. 31. Horlait, D., Claparede, L., Tocino, F., Clavier, N., Ravaux, J., Szenknect, S., Podor, R., & Dacheux, N. (2014). Environmental SEM monitoring of Ce1-xLnxO2-x/2 mixed-oxide microstructural evolution during dissolution. J. Mater. Chem., 2, 5193-5203, DOI: 10.1039/C3TA14623E.
    Open DOISearch in Google Scholar
  32. 32. Suárez, M. F., & Compton, R. G. (1998). Dissolution of magnesium oxide in aqueous acid: An atomic force microscopy study. J. Phys. Chem. B, 102, 7156-7162. DOI: 10.1021/jp982260x.
    Open DOISearch in Google Scholar
  33. 33. Tytko, K. H. (1989). Mo: Molybdenum. System number 53. Molybdenum oxide hydrates, oxomolybdenum species in aqueous solutions. Berlin: Springer.
    Search in Google Scholar
  34. 34. Fujii, T., Yamana, H., Watanabe, M., & Moriyama, H. (2001). Extraction of molybdenum from nitric acid by octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide. Solvent Extr. Ion Exch., 19, 127-141. DOI: 10.1081/sei-100001378.
    Open DOISearch in Google Scholar
  35. 35. Saito, A., & Choppin, G. R. (1998). Complexation of uranyl(VI) with polyoxometalates in aqueous solutions. J. Alloys Compd., 271/273, 751-755. DOI: 10.1016/S0925-8388(98)00200-X.
    Open DOISearch in Google Scholar
  36. 36. Suzuki, H., Sasaki, Y., Sugo, Y., Apichaibukol, A., & Kimura, T. (2004). Extraction and separation of Am(III) and Sr(II) by N,N,N',N'-tetraoctyl-3-oxapentanediamide (TODGA). Radiochim. Acta, 92, 463-466. DOI: 10.1524/ract.92.8.463.39276.
    Open DOISearch in Google Scholar
  37. 37. Ansari, S. A., Pathak, P. N., Manchanda, V. K., Husain, M., Prasad, A. K., & Parmar, V. S. (2005). N,N,N',N'-Tetraoctyl diglycolamide (TODGA): a promising extractant for actinide partitioning from high-level waste (HLW). Solvent Extr. Ion Exch., 23, 463-479. DOI: 10.1081/sei-200066296.
    Open DOISearch in Google Scholar
  38. 38. Cuillerdier, C., Musikas, C., Hoel, P., Nigond, L., & Vitart, X. (1991). Malonamides as new extractants for nuclear waste solutions. Separ. Sci. Technol., 26, 1229-1244. DOI: 10.1080/01496399108050526.
    Open DOISearch in Google Scholar
  39. 39. Cuillerdier, C., Musikas, C., & Nigond, L. (1993). Diamides as actinide extractants for various waste treatments. Separ. Sci. Technol., 28, 155-175. DOI: 10.1080/01496399308019484.
    Open DOISearch in Google Scholar
DOI: https://doi.org/10.1515/nuka-2015-0124 | Journal eISSN: 1508-5791 (formerly 0029-5922) | Journal ISSN: 0029-5922
Journal RSS Feed
Language: English
Page range: 871 - 878
Submitted on: Jun 19, 2015
Accepted on: Sep 15, 2015
Published on: Dec 30, 2015
Published by: Institute of Nuclear Chemistry and Technology
In partnership with: Paradigm Publishing Services
Keywords:
CERCER,
CERMET,
dissolution,
inert matrix fuels (IMF),
liquid-liquid extraction,
minor actinides,
reprocessing
Related subjects:
Chemistry,
Nuclear chemistry

© 2015 Elena L. Ebert, Andrey Bukaemskiy, Fabian Sadowski, Steve Lange, Andreas Wilden, Giuseppe Modolo, published by Institute of Nuclear Chemistry and Technology
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 License.

Volume 60 (2015): Issue 4 (December 2015)
Previous article
Next article