Karel Lemmens

Person

Lemmens, Karel

  • R&D Waste Packages

Person: Employee

  1. 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-ST67

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  2. Mechanisms governing the release of radionuclides from spent nuclear fuel in geological repository: Major outcomes of the European Project SFS

    Poinssot, C., Ferry, C., Grambow, B., Kelm, M., Spahiu, K., Martinez, A., Johnson, L., Cera, E., de Pablo, J., Quinones, J., Wegen, D., Lemmens, K., McMenamin, T. & Cachoir, C., Jun 2006, Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, p. 421-432

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  3. 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: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  4. 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. 39-42

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  5. Transport- and surface reaction-controlled SON68 glass dissolution at 30°C and 70°C and pH = 13.7

    Liu, S., Ferrand, K. & Lemmens, K., Oct 2015, In: Applied Geochemistry. 61, 10, p. 302-311 9 p.

    Research output: Contribution to journalArticlepeer-review

  6. Bituminised Waste Re-treatment: Replacement of the Bitumen Matrix by a Glass Matrix

    Impens, N., Tennstedt, I., Lemmens, K., Gielen, B., Van Laer, J., Fonteyne, A., Vos, L., Vos, B., Leenaers, A., Van den Berghe, S., Van Bree, P., Van Oost, G. & Van Iseghem, P., Jun 2006, Scientific Basis for Nuclear Waste Management XXIX. Warrendale, PA, Belgium, Vol. 1. p. 743-750 (MRS Proceedings; no. Volume 932).

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  7. 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: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  8. The Interaction Between Nuclear Waste Glass and Ordinary Portland Cement

    Ferrand, K., Liu, S. & Lemmens, K., Dec 2013, In: International Journal of Applied Glass Science. 4, 4, p. 328-340

    Research output: Contribution to journalArticlepeer-review

  9. Obtaining solubility constants to describe the incongruent dissolution of SON68 waste glass by an equilibrium ideal solid solution model approach

    Jacques, D. & Lemmens, K., Jun 2006, Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, p. 337-344

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

ID: 29874