Katrien Van Tichelen

Person

Van Tichelen, Katrien

  • LBE Components and Experiments

Person: Employee

  1. 2019
  2. MYRRHA primary heat exchanger experimental simulations on CIRCE-HERO

    Lorusso, P., Pesetti, A., Barone, G., Castelliti, D., Forgione, N., Giannetti, F., Martelli, D., Rozzia, D., Van Tichelen, K. & Tarantino, M. 3 Nov 2019 In : Nuclear Engineering and Design. 353, p. 1-10 10 p., 110270

    Research output: Contribution to journalArticle

  3. Thermal Hydraulic Aspects of Liquid Metal Cooled Reactors

    Roelofs, F. (ed.), Van Tichelen, K., Kennedy, G., Rozzia, D., Castelliti, D., Keijers, S. & Fernandez, R. 4 Sep 2019 Duxford, UK: Woodhead publishing (imprint of Elsevier). 462 p. (Energy)

    Research output: Report/bookBook as author

  4. A Collaborative Effort Towards the Accurate Prediction of Turbulent Flow and Heat Transfer in Low-Prandtl Number Fluids

    Shams, A., Roelofs, F., Tiselj, I., Bartosiewicz, Y., Niceno, B., Duponcheel, M., Guo, W., Stalio, E., Angeli, D., Fregni, A., Koloszar, L., Villa Ortiz, A., Planquart, P., Narayanan, C., Lakehal, D., Van Tichelen, K., Jäger, W. & Schaub, T. 18 Aug 2019 18th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). American Nuclear Society, 15 p.

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

  5. CFD and Experiments for Wire-wrapped Fuel Assemblies

    Roelofs, F., Uitslag-Doolaard, H., Mikuz, B., Dovizio, D., De Santis, D., Shams, A., Bertocchi, F., Rohde, M., Van Tichelen, K., Keijers, S., Kennedy, G., Batta, A., Julio, P., Planquart, P., Obabko, A., Brockmeyer, L., Merzari, E., Vaghetto, R., Hassan, Y., Leonard, D., Martin, M., Steer, M., Delchini, M. & Pointer, W. D. 18 Aug 2019 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). American Nuclear Society, p. 1-14 14 p.

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

  6. Fouling effect of lead oxide crystallization on heat transfer in LBE

    Shin, Y-H., Gladinez, K., Lim, J., Marino, A., Rosseel, K., Aerts, A. & Van Tichelen, K. 18 Aug 2019 International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). American Nuclear Society, 14 p.

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

  7. Heavy Liquid Metal Thermal Hydraulic Progress in the MYRTE Project

    Roelofs, F. & Van Tichelen, K. 18 Aug 2019 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). American Nuclear Society, p. 1-14 14 p.

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

  8. Numerical simulation of loss-of-flow transient in the MYRRHA reactor

    Koloszar, L., Planquart, P., Van Tichelen, K. & Keijers, S. 18 Aug 2019 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). American Nuclear Society, p. 1-14 14 p.

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

  9. Numerical simulations of the turbelence-induced vibrations of a wire-wrapped hexagonal fuel assembly

    Dolfen, H., De Ridder, J., Brockmeyer, L., Merzari, E., Kennedy, G., Van Tichelen, K. & Degroote, J. 18 Aug 2019 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). American Nuclear Society, p. 5092-5102 11 p.

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

  10. Results on thermal hydraulic experiments in the LBE-cooled scaled pool facility E-scape in support of the MYRRHA design and licensing

    Van Tichelen, K. & Mirelli, F. 18 Aug 2019 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18. American Nuclear Society, p. 1-11 11 p.

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

  11. Validation of CFD analyses against pool experiments E-scape

    Visser, D., Roelofs, F., Mirelli, F. & Van Tichelen, K. 18 Aug 2019 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18. American Nuclear Society, p. 1-11 11 p.

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

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ID: 33264