Research output per year
Research output per year
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Boundary conditions to water removal from defective spent fuel
Verwerft, M., Cornelis, G., Pakarinen, J., Faber, W., Höfer, H. & Rirschl, C., 22 Sep 2019, Top Fuel 2019. 2019 ed. Seattle: Unknown, p. 94-103 10 p.Research output › peer-review
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First phase of the spent fuel autoclave leaching experiments (SF-ALE) at sck cen
Mennecart, T., Leinders, G., Cachoir, C., Cornelis, G., Verpoucke, G., Modolo, G., Bosbach, D., Lemmens, K. & Verwerft, M., 22 Sep 2019, GLOBAL/TOPFUEL 2019. American Nuclear Society, p. 1-8 8 p.Research output › peer-review
Open AccessFile68 Downloads (Pure) -
Effect of fission rate on the microstructure of coated UMo dispersion fuel
Leenaers, A., Parthoens, Y., Cornelis, G., Kuzminov, V., Van den Berghe, S., Koonen, E., Ye, B., Hofmann, G. L. & Schulthess, J., 1 Oct 2017, In: Journal of Nuclear Materials. 494, p. 10-19 10 p., 494.Research output › peer-review
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Experimental setup for hydraulic resistance measurements on spent nuclear fuel
Cornelis, G., Pakarinen, J., Faber, W. & Verwerft, M., 12 Dec 2017, http://hotlab.sckcen.be/en/Proceedings. SCK CEN, p. 1-7 7 p.Research output › peer-review
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Swelling of U(Mo) dispersion fuel under irradiation – Non-destructive analyses of the SELENIUM plates
Van den Berghe, S., Parthoens, Y., Cornelis, G., Leenaers, A., Koonen, E., Kuzminov, V., Detavernier, C. & Sannen, L. (Peer reviewer), 22 Aug 2013, In: Journal of Nuclear Materials. 442, 1-3, p. 60-68Research output › peer-review
Open Access