Research output per year
Research output per year
- 12 results
Search results
-
2019
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 AccessFile53 Downloads (Pure) -
2016
Uranium dissolution in hyperalkaline TMA-OH solutions: Preliminary results
Cachoir, C., Salah, S., Mennecart, T. & Lemmens, K., 1 Dec 2016, ATALANTE 2016 INTERNATIONAL CONFERENCE ON NUCLEAR CHEMISTRY FOR SUSTAINABLE FUEL CYCLES: 5th International ATALANTE International Conference on Nuclear Chemistry for Sustainable Fuel Cycles. Vol. 21. p. 306-313 (Procedia Chemistry).Research output › peer-review
Open Access -
2014
FIRST-Nuclides: Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel
Kienzler, B., Metz, V., González-Robles, E., Duro, L., Vals, A., Wegen, D., Carbol, P., Serrano-Purroy, D., Curtius, H., Günther-Leopold, I., Froideval Zumbieh, A., Curti, E., Lemmens, K., Vandenborre, J., de Pablo, J., Casas, I., Clarens, F., Hózer, Z., Roth, O. & Mennecart, T., Dec 2014, Conference Proceedings EURADWASTE ’13. Spain, Vol. 1. p. 221-228Research output › peer-review
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2012
Characterisation of SCK-CEN fuel samples used for leach tests in FIRST-Nuclides
Govers, K., Verwerft, M., Van Renterghem, W., Lemmens, K., Mennecart, T., Cachoir, C., Adriaensen, L., Dobney, A. & Gysemans, M., 10 Oct 2012, 1st Annual Workshop Proceedings - 7th EC - FP First-Nuclides. Budapest, Hungary, p. ST61-ST67Research output › peer-review
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Corrosion behavior of spent nuclear fuel in high pH solutions – Effect of hydrogen
Loida, A., Gens, R., Bube, C., Lemmens, K., Cachoir, C., Mennecart, T. & Kienzler, B., Dec 2012, MRS Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXXV. United States, p. 119-124 (MRS Symposium Proceedings; no. 1475).Research output › peer-review
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Effect of a cement buffer on Spent Fuel dissolution
Mennecart, T., Cachoir, C., Lemmens, K., Gielen, B., Vercauter, R. & Druyts, F., Mar 2012, Cementitious materials in safety cases for geological repositories for radioactive waste: role, evolution and interaction. Paris, France, p. 199-203 (NEA/RWM report; no. NEA/RWM/R(2012)3).Research output › peer-review
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Interaction of cementitious materials with high-level waste matrices
Lemmens, K., Cachoir, C., Ferrand, K., Mennecart, T., Gielen, B., Vercauter, R. & Druyts, F., Mar 2012, Cementitious materials in safety cases for geological repositories for radioactive waste: role, evolution and interaction. Paris, France, p. 129-130 (NEA/RWM report; no. NEA/RWM/R(2012)3).Research output › peer-review
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Spent fuel dissolution in Belgian Supercontainer conditions: Source term and compatibility
Lemmens, K., Mennecart, T., Cachoir, C. & Kursten, B., Dec 2012, MRS Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXXV. United States, p. 131-136 (MRS Symposium Proceedings; no. 1475).Research output › peer-review
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UO2 dissolution in high pH conditions of the Belgian Supercontainer
Mennecart, T., Cachoir, C. & Lemmens, K., Dec 2012, MRS Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXXV. United States, p. 293-298 (MRS Symposium Proceedings; no. 1475).Research output › peer-review
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2009
Corrosion Behavior of High Burnup Spent Fuel in Highly Alkaline Solutions
Loida, A., Gens, R., Metz, V., Lemmens, K., Cachoir, C., Mennecart, T., Kienzler, B. & Ferrand, K., Dec 2009, Scientific Basis for Nuclear Waste Management XXXIII. Symposium Proceedings. Volume 1193. Warrendale, PA, United States, p. 597-604 (Materials Research Society proceedings; no. Volume 1193).Research output › peer-review
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2008
The strategy of the Belgian nuclear research centre in the area of high level waste form compatibility research
Lemmens, K., Cachoir, C., Valcke, E., Ferrand, K., Aertsens, M. & Mennecart, T., May 2008, The 11th International Conference on Environmental Remediation and Radioactive Waste Management. Fairfield, NJ, United States, p. 1-8Research output › peer-review
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2007
Dissolution behaviour of UO2 in anoxic conditions. Comparison of Ca-bentonite and Boom Clay
Mennecart, T., Cachoir, C., Lemmens, K., Volckaert, G. & Wang, L., Dec 2007, Scientific Basis for Nuclear Waste Management XXX, MRS Proceedings Volume 985. Warrendale, Pennsylvania, United States, p. 39-42Research output › peer-review