Steven Keijers

Research output

Research output per year 2011 2013 2015 2019 2020 2022 2024

• 21 In-proceedings paper
• 14 Article
• 2 Master's thesis
• 1 Book as author
• 2 More
  • 1 Special issue
  • 1 Review article

Research output per year

Research output per year

Search results

• 2023

  Analysis of the Anisotropic Term in the Implicit Algebraic Heat Flux Model in the Case of Low Prandtl Flow in Planar Impinging Jet Case

  Oder, J., Coëpeau, A., Koloszar, L., Laboureur , D. & Keijers, S., 25 Aug 2023, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) . Washington, D.C.: American Nuclear Society, p. 832-845 14 p.

  Research output › peer-review

  Open Access

• Analysis of the Scaling between Model Experimental Facilities MYRRHABELLE and E-SCAPE and the MYRRHA reactor augmented by CFD

  Koloszar, L., Lopes, S., Faruoli, M., Planquart, P., Van Tichelen, K., Pacio, J. & Keijers, S., 20 Aug 2023, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) . American Nuclear Society, p. 1136-1149 14 p.

  Research output › peer-review

  Open Access
• 2022

  CFD simulation of the heavy liquid European scaled pool experiment (E-SCAPE)

  Lopes, S., Koloszar, L., Planquart, P., Van Tichelen, K. & Keijers, S., 6 Mar 2022, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) . SCK CEN, p. 1-14 14 p. 35782

  Research output › peer-review

• Comparison o RANS and LES heat transfer results for a 19-rod bundle experiment with wire spaces cooled by lead bismuth eutectic

  Uitslag-Doolaart, H. J., Roelofs, F., Brockmeyer, L., Degroote, J., Dolfen, H., Di Piazza, I., Marinari, R., Pacio, J., Keijers, S. & Van Tichelen, K., 6 Mar 2022, 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics: (NURETH19). Belgium, Brussels: American Nuclear Society, 16 p.

  Research output › peer-review

• Conjugate heat transfer and boundary condition phenomena in rod bundle experiments with liquid metals

  Keijers, S., Fiore, S. A., Pacio, J. & Van Tichelen, K., 6 Mar 2022, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics: NURETH19. 2022 ed. Mol, Belgium: SCK CEN, 16 p. 35892

  Research output › peer-review

  Open Access
• 2019

  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 › peer-review

  Open Access

• CFD Analyses of the European Scaled Pool Experiment E-Scape

  Visser, D., Keijers, S., Lopes, S., Roelofs, F., Van Tichelen, K. & Koloszar, L., 19 Mar 2019, SESAME International Workshop. Unknown, p. 1-9 9 p.

  Research output › peer-review

• 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. & 4 others, 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 › peer-review

• Numerical and Experimental Analysis on a Planar Jet with Heated Co-Flow at Medium- and Low-Prandtl Number Values

  Cascioli, E., Buckingham, S., Villa Ortiz, A., Keijers, S., Van Tichelen, K. & Kenjeres, S., 19 Mar 2019, SESAME International Workshop. Unknown, p. 1-8 8 p.

  Research output › peer-review

• 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 › peer-review

• 2015

  CFD Benchmark for a Heavy Liquid Metal Fuel Assembly

  Doolaard, H., Shams, A., Roelofs, F., Van Tichelen, K., Keijers, S., De Ridder, J., Degroote, J., Vierendeels, J., Di Piazza, I., Merzari, E., Obabko, A. & Fischer, P., Aug 2015, International Topical Meeting on Nuclear Reactor Thermal Hydraulics. United States

  Research output › peer-review

• CFD Simulations to Determine the Effects of Deformations on Liquid Metal Cooled Wire Wrapped Fuel Assemblies

  Sosnovsky, E., Baglietto, E., Keijers, S., Van Tichelen, K., Cardozo de Souza, T., Doolaard, H. & Roelofs, F., 30 Aug 2015, 16th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16).

  Research output › peer-review

• MYRRHA foam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA

  Koloszar, L., Buckingham, S. & Keijers, S., Sep 2015, International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, Vol. 3. p. 2237-2250 14 p. (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; vol. 3).

  Research output › peer-review

• Pre-test computational fluid dynamics and system thermal hydraulics calculations of the e-scape scaled lbe pool facility

  Greco, M., Mirelli, F., Keijers, S. & Van Tichelen, K., 30 Aug 2015, 16th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16).

  Research output › peer-review

• 2014

  E-SCAPE: A scale facility for liquid-metal, pool-type reactor thermal hydraulic investigations

  Van Tichelen, K., Mirelli, F., Greco, M., Viviani, G. & Keijers, S. (Peer reviewer), Jan 2014, THINS 2014 International Workshop. Italy

  Research output › peer-review

• Large-Eddy Simulations of Turbulence-induced Vibration in Annular Flow

  De Ridder, J., Degroote, J., Vierendeels, J., Van Tichelen, K., Schuurmans, P. & Keijers, S. (Peer reviewer), 20 Jul 2014, Proceedings ASME 2014 Pressure Vessels and Piping Conference ; Volume 4: Fluid-Structure Interaction. United States, Vol. 4. (ASME Pressure Vessels and Piping Conference).

  Research output › peer-review
• 2013

  Modal Characteristics of a Flexible Tube in Turbulent Axial Flow: a Numerical Approach and Validation with Experimental Data

  De Ridder, J., Degroote, J., Van Tichelen, K., Schuurmans, P., Vierendeels, J. & Keijers, S. (Peer reviewer), Jun 2013, Computational Methods for Coupled Problems in Science and Engineering V. Spain, p. 669-676

  Research output › peer-review

• Numerical computation on modal characteristics of a clamped-clamped cylinder in turbulent axial pipe flow

  De Ridder, J., Degroote, J., Vierendeels, J., Van Tichelen, K., Schuurmans, P. & Keijers, S. (Peer reviewer), Jul 2013, ASME 2013: Pressure Vessels & Piping Conference. United States

  Research output › peer-review

• Status and future challenges of CFD for liquid metal cooled reactors

  Roelofs, F., Gopala, V., Van Tichelen, K., Cheng, X., Merzari, E., Pointer, W. D. & Keijers, S. (Peer reviewer), Mar 2013, International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13). Vienna, Austria

  Research output › peer-review

• 2012

  Partitioned simulation of long and slender cylinders corresponding to nuclear fuel rods vibrating in axial flow

  De Ridder, J., Degroote, J., Van Tichelen, K., Vierendeels, J. & Keijers, S. (Peer reviewer), Sep 2012, European Congress on Computational Methods in Applied Sciences and Engineering (ECCOMAS 2012). Vienna, Austria, p. 1823-1832 10 p. (ISBN: 978-3-9503537-0-9).

  Research output › peer-review

• 2011

  Scaling Analysis for the European Heavy Liquid Metal Scaled Pool Facility Escape

  Van Tichelen, K., Vanderhaegen, M., Jayaraju, S., Keijers, S., Roelofs, F. & Greco, M. (Peer reviewer), 26 Sep 2011, The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics. Toronto, Canada

  Research output › peer-review