Karel Lemmens

Person

Lemmens, Karel

  • R&D Waste Packages

Person: Employee

  1. In-proceedings paper › Research › Peer-reviewed
  2. Chemical durability of high-level waste glass in repository environment: main conclusions and remaining uncertainties from the GLASTAB and GLAMOR projects

    Van Iseghem, P., Lemmens, K., Aertsens, M., Gin, S., Ribet, I., Grambow, B., Crovisier, J. L., Del Nero, M., Curti, E., Schwyn, B., Luckscheiter, B., McMenamin, T. & Volckaert, G., Jun 2006, Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, p. 293-304

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

  3. CORALUS: an integrated in situ test on the corrosion of alpha-active (SON68) HLW glass

    Valcke, E., Smets, S., Labat, S., Lemmens, K., Van Iseghem, P., Thomas, P., Godon, N., Jollivet, P., Parisot, G., Mestre, J-P., Jockwer, N., Wieczorek, K. & Pozo, C., Jun 2006, Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, p. 67-78

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

  4. CORALUS: an integrated in situ test on the corrosion of α-active (SON68) HLW glass

    Valcke, E., Lemmens, K., Van Iseghem, P., Godon, N., Jollivet, P., Jockwer, N., Wieczorek, K. & Pozo, C., Nov 2008, Radioactive waste disposal in geological formations. Proceedings. Braunschweig, Germany, Vol. 1. p. 187-198

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

  5. 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

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

  7. Determination of dissolution rates in vitrified high and medium level waste in a cementitious environment

    Ferrand, K., 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. 205-208 (NEA/RWM report; no. NEA/RWM/R(2012)3).

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

  8. Determination of the forward rate of dissolution for SON68 and PAMELA glasses in contact with alkaline solutions

    Ferrand, K. & Lemmens, K., Sep 2008, Scientific Basis for Nuclear Waste Management XXXI. Warrendale, PA, United States, p. 287-294 (MRS Proceedings; no. 1107).

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

  9. 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

  10. Dissolution of plasma treated non-radioactive surrogate cemented concentrates and ion exchange resins in KOH solution at 40 °C

    Ferrand, K., Caes, S., Lemmens, K. & Meert, K., 22 Apr 2020, IOP Conference Series: Materials Science and Engineering. 2020 ed. IOP Publishing, Vol. 818. p. 1-9 9 p. 012016

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

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

ID: 29874