1st Annual Meeting of the ATLANTIC (Accident tolerant fuels in recycling) consortium (22 January 2020, Manchester, UK)
Synthesis, characterisation and preliminary dissolution assessment of Cr-doped UO2 fuel. Smith, H., Cordara, T., Mohun, R., Stennett, M., Hyatt, N., Corkhill, C. (UFSD) Presentation
Annual Joint Winter School for the Nuclear Centres for Doctoral Training (9 January 2020, York, UK)
Advanced nuclear fuel in disposal conditions. Smith, H., Cordara, T., Mohun, R., Stennett, M., Hyatt, N., Corkhill, C. (UFSD) Poster
9th Conference on Euratom Research and Training in Radioactive Waste Management – EURADWASTE’19 (4-7 June 2019, Pitesti, Romania)
Spent fuel alteration model integrating processes of different time-scales. Riba, O., Coene, E., Silva O., Duro, L. (AMPHOS21). Poster
Chromium doped UO2-based Model Systems: the Model Materials for the Study of the Matrix Corrosion of Modern Spent Nuclear Fuels. Kegler, P., Klinkenberg, M., Bukaemskiy, A., Deissmann, G., Bosbach, D., Alekseev E.V. Delville, R., Cachoir, C., Mennecart, T., Lemmens, K., Verwerft, M. (JUELICH) Poster
17th International Conference on the Chemistry and Migration Behaviour of Actinides and Fission Products in the Geosphere – MIGRATION 2019 (15 - 20 September 2019, Kyoto, Japan)
Stability of chromium - aluminium doped fuel and dissolution results. Fernández, S., Rodríguez-Villagra, N., Bonales, L.J., Gutiérrez, L., Milena-Pérez, A., Cobos, J. (CIEMAT). Poster
Leaching of homogeneous MOx peller U0.73Pu0.27O2 in carbonated water and clayey groundwater with metal iron. Kerleguer, V., Jégou, C., De Windt, L., Broudic, V., Martin, C., Tocino, F. (JUELICH) Presentation
43th Annual Symposium on the Scientific Basis for Nuclear Waste Management (21-24 October 2019, Vienna, Austria)
Hot Isostatic Pressing (HIP): a new method to prepare Cr-doped UO2 modern nuclear fuel. Cordara, T. Smith, H. Mohun, R. Gardner, L. Stennett, M. Hyatt, N., Corkhill C. (UFSD)
Aqueous leaching of ADOPT and standard UO2 spent nuclear fuel under H2 atmosphere. Barreiro Fidalgo, A., Roth, O., Puranen, A., Evins, L.Z., Spahiu, K. (Studsvik, SKB) Presentation.
Spent fuel alteration model integrating processes of different time-scales. Riba, O., Coene, E., Silva, O., Duro L. (A21) Presentation
30th Spent Fuel Workshop (14-15 November 2019, Ghent, Belgium)
High Burnup Spent Fuel dissolution under highly alkaline conditions. Iglesias, L., Serrano Purroy, D., Martínez Torrents, A., Clarens, F., de Pablo, J., Casas, I. (JRC, EURECAT) Presentation.
Alteration of advanced doped UO2 fuel in repository conditions. Rodríguez-Villagra, N., Fernández, S., Bonales, L.J., Milena-Pérez, A., Nuñez, A. Nebot, L., Durán, S., Anta, L., Serrano, L., Cobos, J. (CIEMAT) Presentation.
Synthesis, characterization and preliminary dissolution assessment of Cr-doped UO2. Smith, H., Cordara, T., Mohun, R., Stennett, M., Hyatt N., Corkhill C. (UFSD) Presentation.
Spent Fuel Alteration Model Integrating Processes of Different Time Scales Implementation and Validation. Riba, O., Coene, E., Silva, O., Duro L. (A21) Presentation.
UO2-based model systems: Model materials for studying the matrix corrosion of spent nuclear fuels. Kegler, P., Klinkenberg, M., Bukaemskiy, A., Brandt, F., Deissmann, G., Bosbach, D. (JUELICH) Presentation
45th Spanish Nuclear Society Annual Meeting (23-28 September 2019, Vigo, Spain)
Fabricación de combustibles dopados: comparación entre distintos métodos de dopaje y determinación de las propiedades físicas. Fernandez Carretero, S., Gutiérrez Nebot, L., Jiménez Bonales, L., Milena Pérez, A., Núñez, A., Rodriguez-Villagra, N., Cobos Sabaté J. (CIEMAT) Presentación
Goldschmidt 2019 (18-23 August 2019, Barcelona, Spain)
Deep geological disposal of used nuclear fuel: Studies on irradiated MOX and related model systems. D. Bosbach, P. Kegler, F. Brandt, G. Deissmann, A. Bukaemskiy, E. Alekseev, P. Kowalski, M. Verwerft, G. Leinders, T. Mennecart, K. Lemmens (JUELICH) Presentation
Uranium 2019 Conference (21-22 January 2019, Bristol, UK)
Preparation of hot isostatically pressed Cr-doped UO2 fuel for dissolution studies. Cordara, T. (UFSD) Presentation
MRS Fall Meeting & Exhibit (25-30 November 2018, Boston, USA)
Effect of Nuclear Fuel Additives on the Spent Nuclear Fuel Reprocessing Dissolution Step. Cordara, T., Smith, H., Corkhill, C.L., Stennett, M., Hyatt, N. (UFSD) Presentation
Chromium Doped UO2-Based Model Systems—Synthesis and Characterization of Model Materials for the Study of the Matrix Corrosion of Spent Modern Nuclear Fuels. Kegler, P., Brandt, F., Lange, S., Klinkenberg, M., Bukaemskiy, A., Deissmann, G., Finkeldei, S., Bosbach, D. (JUELICH) Presentation
29th Spent Fuel Workshop (17-18 May 2018, Sheffield, UK)
Effect of environmental conditions on the radiolytic dissolution of homogeneous (25% Pu) MOx pellets. Kerleguer, V., Jégou, C., De Windt, L., Broudic, V., Martin, C. (JUELICH) Presentation
High Burnup Spent Fuel dissolution under highly alkaline conditions. Iglesias, L., Serrano-Purroy, D., Martínez-Torrents, A., Pablo, J., Casas, I. (JRC) Presentation
Kerleguer, V., Jégou, C., De Windt, L., Broudic, V., Jouan, G., Miro, S., Tocino, F. and Martin, C. (2020). The mechanisms of alteration of a homogeneous U0.73Pu0. 27O2 MOx fuel under alpha radiolysis of water. Journal of Nuclear Materials, 529, 151920.
https://www.sciencedirect.com/science/article/pii/S0022311519307755
Milena-Pérez, A., Bonales, L.J., Rodríguez-Villagra, N., Fernández, S., Baonza, V.G. and Cobos, J. (2021) Raman spectroscopy coupled to principal component analysis for studying UO2 nuclear fuels with different grain sizes due to the chromia addition. Journal of Nuclear Materials, 543, 152581.
https://www.sciencedirect.com/science/article/pii/S0022311520311892
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