Steven Keijers

Person

Keijers, Steven

  • Nuclear Technology Engineering

Person: Employee

  1. 2019
  2. 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

  3. 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

  4. 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

  5. NUMERICAL SIMULATIONS OF THE TURBULENCE-INDUCED VIBRATIONS OF A WIRE-WRAPPED HEXAGONAL FUEL ASSEMBLY

    Keijers, S., Fernandez, R., 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, 11 p.

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

  6. An improved CFD model for a MYRRHA based primary coolant loop

    Moreau, V., Profir, M., Keijers, S. & Van Tichelen, K. 22 Jul 2019 In : Nuclear Engineering and Design. 353, p. 1-13 13 p., 110221

    Research output: Contribution to journalArticle

  7. An Improved CFD Model for a MYRRHA based Primary Coolant Loop

    Moreau, V., Profir, M., Keijers, S. & Van Tichelen, K. 19 Mar 2019 SESAME International Workshop Petten, The Netherlands, 19-21 March 2019 - 2019 : Workshop Paper. 2019 ed. Pette, The Netherlands: Unknown, p. 1-14 14 p.

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

  8. 2018
  9. Numerical modeling of iron-based corrosion product oxides mass transport in the MYRRHA reactor during normal operation

    Marino, A., Buckingham, S., Gladinez, K., Keijers, S., Planquart, P., Van Tichelen, K. & Aerts, A. 27 Aug 2018 In : Nuclear Engineering and Design. 338, p. 199-208 10 p.

    Research output: Contribution to journalArticle

  10. Numerical modeling of oxygen mass transfer in a wire wrapped fuel assembly under flowing lead bismuth eutectic

    Marino, A., Lim, J., Keijers, S., Aerts, A. & Deconinck, J. 1 Aug 2018 In : Journal of Nuclear Materials. 506, p. 53-62 9 p.

    Research output: Contribution to journalArticle

  11. 2016
  12. MyrrhaFoam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA

    Keijers, S., Koloszar, L., Buckingham, S. & Planquart, P. 3 Jun 2016 In : Nuclear Engineering and Design. 312, p. 256-265

    Research output: Contribution to journalArticle

  13. Benchmark exercise for fluid flow simulations in a liquid metal fast reactor fuel assembly

    Merzari, E., Fischer, P., Yuan, H., Van Tichelen, K., Keijers, S., De Ridder, J., Degroote, J., Vierendeels, J., Doolaard, H., Gopala, V. & Roelofs, F. 1 Mar 2016 In : Nuclear Engineering and Design. 298, p. 218-228

    Research output: Contribution to journalArticle

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ID: 39580