Nuclear Technology Engineering

Research output

Research output per year 2017 2019 2022 2024

• 19 In-proceedings paper
• 16 Article
• 5 Master's thesis
• 2 Chapter
• 3 More
  • 1 Book as author
  • 1 ER - External report
  • 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

• Civil and structural design for MYRRHA

  Moretti, G., Engelen, J., Kennedy, G., Greco, M., Naumov, T., Andreev, S. & O'LMalley, D., 15 Sep 2023, (Submitted) TINCE 2023 – Technological Innovations in Nuclear Civil Engineering. France: Sfen - Société française d’énergie nucléaire, 12 p.

  Research output › peer-review

• Modeling of Table Top Primary Heat Exchanger Experiment RUN#5 by Means of the System Codes RELAP5 mod 3.3 and Flownex SE 8.4

  Rozzia, D., Potgieter, M., Cools, J., Van Loy, T., Kennedy, G., Pacio, J., Van Tichelen, K. & Fernandez, R., 2023, Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. American Nuclear Society, p. 722-735 14 p. 40591. (Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023).

  Research output › peer-review

  Open Access

• Validation in water of a new methodology for the vibrational analysis of rotating components in a high-density fluid

  Ceusters, K., Iarmonov, M., Makhov, K., Van Tichelen, K., Van Damme, M., Dolfen, H., Delaissé, N., Verstraete, T. & Degroote, J., 20 Aug 2023, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 20): Fluid-Structure Interactions. American Nuclear Society, p. 4384-4396 13 p.

  Research output › peer-review
• 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

• Experimental program for demonstrating the timely insertion of safety rods in MYRRHA

  Pacio, J., Lamberts, D. & Van Tichelen, K., 16 Nov 2022, 2022 Winter Post Meeting access. American Nuclear Society, p. 1-3 3 p.

  Research output › peer-review

  Open Access

• Experimental thermal-hydraulic R&D achievements and needs for MYRRHA

  Pacio, J., Van Tichelen, K., Kennedy, G., Iarmonov, M., Rozzia, D., Schuurmans, P. & Fernandez, R., Sep 2022, (Accepted/In press) Unknown. IAEA - International Atomic Energy Agency, p. 1-10 10 p. (Proceedings Series - International Atomic Energy Agency).

  Research output › peer-review

  Open Access

• Predicting fretting wear due to turbulence-induced vibration in a wire-wrapped fuel assembly

  Dolfen, H., De Ridder, J., Brockmeyer, L. A., Merzari, E., Kennedy, G., Van Tichelen, K. & Degroote, J., 6 Mar 2022, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). SCK CEN, p. 1-16 16 p. 35577

  Research output › peer-review

• 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

• Development of the HEXACOM Facility for Characterising the Heat Transfer Performance of the MYRRHA PHX in LBE

  Rozzia, D., Kennedy, G., Mirelli, F. & Van Tichelen, K., 19 Mar 2019, SESAME international workshop. Unknown, p. 1-13 13 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

• 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 › peer-review

  Open Access

• Towards Validated Prediction with RANS CFD of Flow and Heat Transport in a Wire-wrap Fuel Assembly

  Roelofs, F., Uitslag-Doolaard, H., Dovizio, D., Blaz, M., Shams, A., Bertocchi, F., Martin, R., Julio, P., Di Piazza, I., Kennedy, G., Van Tichelen, K., Obabko, A. & Merzari, E., 19 Mar 2019, SESAME international workshop. Unknown, p. 1-11 11 p.

  Research output › peer-review