Karel Lemmens

Person

Lemmens, Karel

  • R&D Waste Packages

Person: Employee

  1. 2022
  2. Topical report on glass dissolution experiments at very high surface area to solution volume

    Ferrand, K., Liu, S., Caes, S. & Lemmens, K., 28 Apr 2022, SCK CEN. 71 p. (SCK CEN Reports; no. ER-1007)

    Research output: Report/bookER - External reportpeer-review

  3. Caesium and iodine release from spent mixed oxide fuels under repository relevant conditions - Initial leaching results

    Schreinemachers, C., Leinders, G., Mennecart, T., Cachoir, C., Lemmens, K., Verwerft, M., Brandt, F., Deissmann, G., Modolo, G. & Bosbach, D., 9 Feb 2022, In: MRS Advances. p. 1-5 5 p.

    Research output: Contribution to journalArticlepeer-review

  4. Static dissolution experiments under hyperalkaline conditions with dispersed and confined SM539 glas

    Ferrand, K., Caes, S., Lemmens, K., Liu, S. & Meert, K., 7 Feb 2022, In: MRS Advances. p. 1-5 5 p.

    Research output: Contribution to journalArticlepeer-review

  5. 2021
  6. Topical report on leaching tests with Simuli-3 plasma slag at 40 °C and in IPM water at pH 12.5: Pre-STABSLAK tests

    Ferrand, K., Caes, S., Lemmens, K. & Valcke, E., 15 Dec 2021, SCK CEN. 33 p. (SCK CEN Reports; no. ER-0936)

    Research output: Report/bookER - External reportpeer-review

  7. Fast release from clad and declad spent UOX PWR fuel segments in a bicarbonate solution under anoxic conditions

    Mennecart, T., Cachoir, C. & Lemmens, K., 3 Sep 2021, In: Journal of Nuclear Materials. 557, p. 1-10 10 p., 153257.

    Research output: Contribution to journalArticlepeer-review

  8. Evolution of the uranium concentration in dissolution experiments with Cr (Pu) doped UO2 in reducing conditions at SCK CEN

    Cachoir, C., Mennecart, T. & Lemmens, K., 18 Mar 2021, In: MRS Advances. 6, p. 84-89 6 p.

    Research output: Contribution to journalArticlepeer-review

  9. Dissolution Kinetics of International Simple Glass and Formation of Secondary Phases at Very High Surface Area to Solution Ratio in Young CementWater

    Ferrand, K., Klinkenberg, M., Caes, S., Poonoosamy, J., Van Renterghem, W., Barthel, J., Lemmens, K., Bosbach, D. & Brandt, F., 6 Mar 2021, In: Materials. 14, 5, p. 1-21 21 p., 1254.

    Research output: Contribution to journalArticlepeer-review

  10. 2020
  11. Topical report on dynamic dissolution tests on SON68, SM513, SM539 and ISG glasses

    Caes, S., Ferrand, K. & Lemmens, K., 15 Oct 2020, SCK CEN. 146 p. (SCK•CEN Reports; no. ER-0729)

    Research output: Report/bookER - External reportpeer-review

  12. 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

  13. 2019
  14. Diffusion models for the early-stage SON68 glass dissolution in a hyper-alkaline solution

    Liu, S., Ferrand, K., Aertsens, M., Jacques, D. & Lemmens, K., 1 Dec 2019, In: Applied Geochemistry. 111, p. 1-12 12 p., 104439.

    Research output: Contribution to journalArticlepeer-review

  15. 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. ANS - American Nuclear Society, p. 1-8 8 p.

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

  16. Leaching tests on plasma treated surrogate waste forms (part II): Topical report

    Ferrand, K., Caes, S. & Lemmens, K., 1 Sep 2019, Studiecentrum voor Kernenergie. 121 p. (SCK•CEN Reports; no. ER-0534)

    Research output: Report/bookER - External reportpeer-review

  17. Dissolution behaviour of vitrified high-level waste in highly alkaline conditions: Phenomenological synthesis report

    Lemmens, K. & Ferrand, K., 30 Jun 2019, Studiecentrum voor Kernenergie. 133 p. (SCK•CEN Reports; no. ER-0559)

    Research output: Report/bookER - External reportpeer-review

  18. Leaching tests on plasma treated surrogate waste forms: Topical report

    Ferrand, K., Caes, S. & Lemmens, K., 1 Mar 2019, Studiecentrum voor Kernenergie. 186 p. (SCK•CEN Reports; no. ER-0516)

    Research output: Report/bookER - External reportpeer-review

  19. Influence of young cement water on the corrosion of the International Simple Glass

    Man, C., Ferrand, K., Liu, S., Eskelsen, J. R., Pierce, E., Lemmens, K. & Corkhill, C., 22 Jan 2019, In: NPJ Materials Degradation . 3, p. 1-9 9 p., 5.

    Research output: Contribution to journalArticlepeer-review

  20. Dissolution behaviour of spent nuclear fuel at highly alkaline conditions: Phenomenological synthesis report

    Lemmens, K., Cachoir, C. & Mennecart, T., 1 Jan 2019, Studiecentrum voor Kernenergie. 103 p. (SCK•CEN Reports; no. ER-0505)

    Research output: Report/bookER - External reportpeer-review

  21. 2018
  22. Integrated leach tests with simulated HLW glass in contact with ordinary Portland cement paste: Topical Report

    Ferrand, K., Liu, S. & Lemmens, K., 1 Nov 2018, Studiecentrum voor Kernenergie. 102 p. (SCK•CEN Reports; no. ER-0431)

    Research output: Report/bookER - External reportpeer-review

  23. 2017
  24. Dynamic experiments: Intermediate topical report

    Mennecart, T., Cachoir, C. & Lemmens, K., 1 Jun 2017, Studiecentrum voor Kernenergie. (SCK•CEN Reports; no. SCK•CEN ER-0385)

    Research output: Report/bookER - External reportpeer-review

  25. Summary of the Euratom Collaborative Project FIRST-Nuclides and Conclusions for the Safety Case

    Kienzler, B., Duro, L., Lemmens, K., Metz, V., de Pablo, J., Valls, A., Wegen, D., Johnson, L. & Spahiu, K., 1 Jun 2017, In: Nuclear Technology. 198, 3, p. 260-276 16 p.

    Research output: Contribution to journalArticlepeer-review

  26. 2016
  27. 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: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

  28. 2015
  29. 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

  30. Iron speciation in soda lime silica glass: a comparison of XANES and UV-vis-NIR spectroscopy

    Ceglia, A., Nuyts, G., Meulebroeck, W., Cagno, S., Silvestri, A., Zoleo, A., Nys, K., Janssens, K., Thienpont, H., Terryn, H. & Lemmens, K., 15 Apr 2015, In: Journal of Analytical Atomic Spectrometry. advance article, issue number/pages will appear later, p. 1-15

    Research output: Contribution to journalArticlepeer-review

  31. 2014
  32. 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. 221-228

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

  33. The effect of Ordinary Portland Cement on nuclear waste glass dissolution

    Ferrand, K., Liu, S. & Lemmens, K., Dec 2014, In: Procedia Materials Science. 7, p. 223-229

    Research output: Contribution to journalArticlepeer-review

  34. 2013
  35. 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

  36. A combined glass dissolution/diffusion experiment in Boom Clay at 30°C

    Aertsens, M., Lemmens, K. & Ferrand, K., May 2013, In: Physics and Chemistry of the Earth. 65, p. 72-78

    Research output: Contribution to journalArticlepeer-review

  37. 2012
  38. 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

  39. 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

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

  41. 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

  42. 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

  43. 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

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

  45. 2011
  46. The interaction between nuclear waste glass and cement

    Ferrand, K., Lemmens, K., Depierre, S. & Cachoir, C., Oct 2011, Proceedings 1st International Symposium on Cement-based Materials for Nuclear Wastes. NUWCEM 2011. Marcoule, France, p. 1-11

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

  47. Glamor- or How We Achieved a Common Understanding on the Decrease of Glass Dissolution Kinetics Through International Cooperation

    Van Iseghem, P., Aertsens, M., Gin, S., Grambow, B., Strachan, D., McGrail, P., Wicks, G., McMenamin, T. & Lemmens, K., Aug 2011, In: Journal of the South Carolina Academy of Science. 9, 1, p. 9-12

    Research output: Contribution to journalArticlepeer-review

  48. 2009
  49. Advances in Integrating European Research on the Near-Field System

    Sneyers, A., Grambow, B., Hernan, P., Alheid, H-J., Aranyossy, J-F., Johnson, L. & Lemmens, K., Dec 2009, Conference proceedings. EURADWASTE'08. EURADWASTE, the Seventh European Commission Conference on the Management and Disposal of Radioactive Waste. Luxembourg, Luxembourg, Vol. 1. p. 161-171 (EUR series; no. 24040).

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

  50. 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

  51. GLAMOR - Or how we achieved a common understanding on the decrease of glass dissolution kinetics

    Van Iseghem, P., Aertsens, M., Gin, S., Deneele, D., Grambow, B., Strachan, D., McGrail, P., Wicks, G. & Lemmens, K., Aug 2009, Environmental Issues and Waste Management Technologies in the Materials and Nuclear Industries XII: Ceramic Transactions, Vol 207. Hoboken (NJ), United States, p. 115-126

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

  52. SCK•CEN R&D on the interaction between nuclear waste glass and clay near- and far-field materials

    Van Iseghem, P., Lemmens, K., Valcke, E. & Aertsens, M., Aug 2009, Environmental Issues and Waste Management Technologies in the Materials and Nuclear Industries XII: Ceramic Transactions, Vol 207. Hoboken (NJ), United States, p. 103-114

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

  53. The leaching of Se, Sn, Zr, Pd from vitrified high-level waste in clay slurries

    Van Iseghem, P., Lemmens, K., Pirlet, V. & De Cannière, P., Aug 2009, Mobile Fission and Activation Products in Nuclear Waste Disposal. Workshop Proceedings. Issy-les-Moulineaux, France, p. 247-257

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

  54. Challenges of assessing long-term performance of nuclear waste matrices in repository near-field environments – insights from the NF-PRO and MICADO projects

    Lemmens, K., Grambow, B., Spahiu, K., Minet, Y., Poinssot, C. & Ferrand, K., Jun 2009, Euradwaste '08. Seventh European Commission Conference on the Management and Disposal of Radioactive Waste. Conference Presentations, Papers and Panel Reports.. Luxembourg, Luxembourg, p. 1-10

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

  55. 2008
  56. 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

  57. 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

  58. Overview and consistency of migration experiments in clay

    Aertsens, M., De Cannière, P., Lemmens, K., Maes, N. & Moors, H., Jun 2008, In: Physics and Chemistry of the Earth. 33, 14-16, p. 1019-1025

    Research output: Contribution to journalArticlepeer-review

  59. 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. 1-8

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

  60. 2007
  61. 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

  62. The BRAG and GM2003 models for glass dissolution

    Aertsens, M., Lemmens, K. & Van Iseghem, P., Dec 2007, Scientific Basis for Nuclear Waste Management XXX, MRS Proceedings Volume 985. Warrendale, Pennsylvania, United States

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

  63. 2006
  64. Comparison of chemiluminescence methods for analysis of hydrogen peroxide and hydroxyl radicals

    Pehrman, R., Amme, M., Cachoir, C., Ferrand, K. & Lemmens, K., Dec 2006, In: Czechoslovak Journal of Physics. 56, Supplement 4, p. D373-D379

    Research output: Contribution to journalArticlepeer-review

  65. 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

  66. 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

  67. 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

  68. Leaching and migration of Np, Pu and Am from alpha-doped SON68 HLW glass in contact with dense clay

    Valcke, E., Gysemans, M., Moors, H., Van Iseghem, P., Godon, N., Jollivet, P. & Lemmens, K., Jun 2006, Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, p. 999-1006

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

  69. 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

  70. 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

  71. Static dissolution tests of alpha-doped UO2 under repository relevant conditions: Influence of Boom Clay and alpha-activity on fuel dissolution rates

    Salah, S., Cachoir, C., Lemmens, K. & Maes, N., Jun 2006, Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, p. 481-488

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

  72. Validation of glass dissolution and Si diffusion parameters with a combined glass dissolution-diffusion experiment in Boom Clay

    Lemmens, K. & Aertsens, M., Jun 2006, Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, p. 329-336

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

  73. 2005
  74. Key components and processes relevant to the alteration of vitrified high-level waste in geological disposal conditions

    Lemmens, K., Godon, N., Gin, S., Minet, Y., Grambow, B. & Aertsens, M., Oct 2005, Proceedings NF-PRO second training course and workshop (on NF-PRO portal). Mol, Belgium, p. 1-9

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

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