1. Experimental measurements and numerical simulations to evaluate the electrode kinetics for 316 stainless steel under PWR-relevant conditions

    Vankeerberghen, M. & Gavrilov, S., 1 Jul 2008, In : Journal of Nuclear Materials. 377, 2, p. 331-339

    Research output: Contribution to journalArticle

  2. Model for a Spinel Oxide Film on an AN Fe-Cr-Ni Alloy, SS304

    Vankeerberghen, M., Aug 2013, 16th International Conference on Environment Degradation of Materials in Nuclear Power Systems - Water reactors. United States

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

  3. 1D steady-state finite-element modelling of a bi-carrier one-layer oxide film

    Vankeerberghen, M., Nov 2006, In : Corrosion Science. 48, 11, p. 3609-3628

    Research output: Contribution to journalArticle

  4. PWR Fatigue Testing at SCK•CEN in the Framework of INCEFA+

    Vankeerberghen, M., Marmy, P. & Bens, L., 15 Jul 2018, Proceedings of the 7th International Conference on Fracture Fatigue and Wear: PWR Fatigue Testing at SCK•CEN in the Framework of INCEFA+. 2019 ed. Springer, p. 225-240 16 p.

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

  5. References to report MRP-431 - Appendix B

    Vankeerberghen, M., 1 Dec 2018, Potential Effects of Hydrogen-Related Degradation on Reactor Pressure Vessel Materials (MRP-431): Review of Current State of Understanding. EPRI - Electric Power Research Institute, p. 1-2 2 p. (Technical report; no. MRP-431 - 3002013225).

    Research output: Contribution to report/book/conference proceedingsChapter

  6. Ensuring data quality for environmental fatique - INCEFA-PLUS testing procedure and data evaluation

    Vankeerberghen, M., Bruchhausen, M., Cicero, R., Doremus, L., Le Roux, J-C., Platts, N., Spätig, P., Twite, M. & Mottershead, K., 15 Jul 2018, Proceedings of the ASME pressure vessels and piping conference. PVP-2018-84081 ed. ASME - The American Society of Mechanical Engineers, Vol. 1A. p. 1-7 7 p. V01AT01A014

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

  7. Gauge-Strain-Controlled Air and PWR Fatigue Life Data for 304 Stainless Steel — Some Eects of Surface Finish and Hold Time

    Vankeerberghen, M., De Smet, M. & Malekian, C., 16 Sep 2020, In : Metals. 2020-10, 1248, p. 1-15 15 p., 10-01248.

    Research output: Contribution to journalArticle

  8. Secondary SCRAM System for Liquid Metal Cooled Nuclear Reactors: Simulation using Particle-Based Methods and Experimental Validation

    Vanmaercke, S., Van den Eynde, G. & Aït Abderrahim, H., Jan 2012, Louvain la Neuve, Belgium: UCL - Université Catholique de Louvain. 211 p.

    Research output: ThesisDoctoral thesis

  9. Conceptual study of a Complementary Scram System For Liquid Metal Cooled Nuclear Reactors

    Vanmaercke, S., Van den Eynde, G., Tijskens, E. & Bartosiewicz, Y., 27 Sep 2009, 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Proceedings. Japan

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

  10. Modelling the Interaction of a Molten Seal and Solid Particles using SPH and DEM Simulations : Application for a Passive New SCRAM System for LMR

    Vanmaercke, S., Van den Eynde, G., Tijskens, E., Bartosiewicz, Y. & Van Tichelen, K., Sep 2011, Nureth-14 Proceedings. Toronto, Canada

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