Katrien Van Tichelen

Research output

Research output per year 2000 2015 2019 2022 2025

• 72 In-proceedings paper
• 45 Article
• 3 Chapter
• 3 Special issue
• 7 More
  • 1 Book of abstracts
  • 1 BLG - Open report
  • 1 Book as author
  • 1 ER - External report
  • 1 Review article
  • 1 Doctoral thesis
  • 1 Master's thesis

Research output per year

Research output per year

Search results

• 2025

  Thermal mixing and stratification in the liquid metal-cooled reactor pool experiment E-SCAPE

  Van Tichelen, K., Mirelli, F., Bartosiewicz, Y. & D'haeseleer, W., Feb 2025, In: Nuclear Engineering and Design. 432, 17 p., 113746.

  Research output › peer-review
• 2024

  Development of a qualified plant nodalization for steady state and transient analysis of table top facility

  Rozzia, D., Dikonimos Makris, L., Cools, J., Van Loy, T., Verpoorten, T. & Van Tichelen, K., 9 Sep 2024, Thermal-Hydraulics and Safety Analysis. ASME - The American Society of Mechanical Engineers, Vol. ICONE31. 9 p. V006T07A107. (Proceedings of 2024 31st International Conference on Nuclear Engineering, ICONE 2024; vol. 6).

  Research output › peer-review

  Open Access

• Factors influencing the behaviour of FBG sensors for temperature measurements

  Carlesi, T., Laboureur, D., Planquart, P., Pacio, J., Van Tichelen, K. & Mégret, P., 2024, Proceedings Advanced Photonics Congress 2024: Signal Processing in Photonic Communications, SPPCom 2024. Optical Society of America (OSA), paper JTu1A.9

  Research output › peer-review

  Open Access

• Multi-scale coupled simulation of E-SCAPE at isothermal conditions

  Hussain, M. M. M. D., Pangukir, F. S. L., Visser, D., Stempniewicz, M. M., Roelofs, F., Pacio, J. & Van Tichelen, K., 27 Aug 2024, 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-14). Vancouver, BC, Canada: Canadian Nuclear Society, 13 p.

  Research output › peer-review

• Numerical analysis of a parallel triple-jet of liquid-sodium in a turbulent forced convection regime

  Cascioli, E., Kaaks, B., Keijers, S., Van Tichelen, K. & Kenjereš, S., Aug 2024, In: International Communications in Heat and Mass Transfer. 156, 107696.

  Research output › peer-review

  Open Access

• Scaling approach and forced-circulation flow patterns in the liquid metal-cooled reactor-pool experiment E-SCAPE

  Van Tichelen, K., Mirelli, F., Greco, M., Bartosiewicz, Y. & D'haeseleer, W., Sep 2024, In: Nuclear Engineering and Design. 426, 17 p., 113361.

  Research output › peer-review
• 2023

  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

• Asymmetric decay heat removal in MYRRHA: experiments in the E-SCAPE facility

  Pacio, J., Serrano Diogo, R. & Van Tichelen, K., 20 Aug 2023, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 20). American Nuclear Society, p. 2986-2999 14 p.

  Research output › peer-review

  Open Access

• Comparison of System Thermal Hydraulic and CFD Analyses of E-SCAPE at forced circulation and under isothermal conditions

  Pangukir, F. S. L., Visser, D., Roelofs, F., Pacio, J. & Van Tichelen, K., 25 Aug 2023, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20). 2023 ed. American Nuclear Society, p. 5048-5057 10 p. 54467

  Research output › peer-review

  Open Access

• Experimental analysis of natural convection in a differentially heated cavity

  Carlesi, T., Oder, J., Laboureur , D., Planquart, P., Pacio, J., Van Tichelen, K. & Mégret, P., Aug 2023, Natural convection: International Heat Transfer Conference 17 . 2023 ed. Begell house Inc., Vol. IHTC-17. 10 p. (International Heat Transfer Conference; vol. IHTC-17).

  Research output › peer-review

• Experimental analysis of natural convection in a differentially heated cavity

  Carlesi, T., Laboureur , D., Planquart, P., Pacio, J., Van Tichelen, K. & Mégret, P., 21 Nov 2023, In: EPJ Web of Conferences. 288, 8 p., 05002.

  Research output › peer-review

  Open Access

• Experimental research of the MYRRHA Primary Pump hydraulic characteristics at a reduced scale

  Iarmonov, M. & Van Tichelen, K., 20 Aug 2023, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 20). American Nuclear Society, Vol. NURETH20. p. 2980-2985 6 p. NURETH20-40249

  Research output › peer-review

  Open Access

• Foreword

  Merzari, E., Roelofs, F., Van Tichelen, K. & Planquart, P., 1 Dec 2023, In: Nuclear Engineering and Design. 414, 112579, 1 p., 112579.

  Research output › peer-review

  Open Access

• 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

  19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics: Official program

  Van Tichelen, K. (Editor), 6 Mar 2022, SCK CEN. 67 p. (SCK CEN Reports; no. NURETH19)

  Research output › peer-review

  Open Access

  File
  480 Downloads (Pure)

• Advanced thermal-hydraulic experiments and instrumentation for heavy liquid metal reactors

  Pacio, J., Van Tichelen, K., Eckert, S., Wondrak, T., Di Piazza, I., Lorusso, P., Tarantino, M., Daubner, M., Litfin, K., Ariyoshi, G., Obayashi, H. & Sasa, T., 1 Dec 2022, In: Nuclear Engineering and Design. 399, p. 1-15 15 p., 112010.

  Research output › peer-review

  Open Access

• Advanced thermal-hydraulic experiments and instrumentation for heavy liquid metal reactors

  Pacio, J., Van Tichelen, K., Eckert, S., Wondrak, T., Di Piazza, I., Lorusso, P. & Tarantino, M., 10 Mar 2022, (Accepted/In press) NURETH-19 - 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics: Brussels, Belgium, March 6 – 11, 2022. American Nuclear Society, p. 1-16 16 p. 19001

  Research output › peer-review

  Open Access

• 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

• Characterization of the velocity field and thermal in a mixed convection context

  Freitas Monteiro, J., Buckingham, S., Planquart, P. & Van Tichelen, K., 6 Mar 2022, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). SCK CEN, p. 1-15 15 p. 36262

  Research output › peer-review

• Combined Large-Eddy and Direct Numerical Simulations of a Planar Jet with Heated Co-Flow with Medium and Low Prandtl Fluids

  Cascioli, E., Keijers, S., Van Tichelen, K., Vesper, J. E. & Kenjeres, S., 26 Mar 2022, In: International Journal of Heat and Mass Transfer. 191, p. 1-17 17 p., 122774.

  Research output › peer-review

  Open Access

• Combining CFD and water model tests for the design of a pool HLM reactor: lessons learned

  Faruoli, M., Planquart, P. & Van Tichelen, K., 6 Mar 2022, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). SCK CEN, p. 1-14 14 p. 36106

  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

• Liquid metal thermal hydraulic activities in European collaborative projects

  Roelofs, F., Tarantino, M., Grasso, G., Van Tichelen, K. & Schuurmans, P., 6 Mar 2022, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). SCK CEN, p. 1-12 12 p. 34010

  Research output › peer-review

• 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

• Validation of natural convection liquid metal flow in the E-SCAPE facility

  Koloszar, L., Lopes, S., Planquart, P. & Van Tichelen, K., 6 Mar 2022, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). SCK CEN, p. 1-13 13 p.

  Research output › peer-review

• 2021

  A multi-stage approach of simulating turbulence-induced vibrations in a wire-wrapped tube bundle for fretting wear prediction

  Dolfen, H., De Ridder, J., Brockmeyer, L., Merzari, E., Kennedy, G., Van Tichelen, K. & Degroote, J., 28 Dec 2021, In: Journal of Fluids and Structures. 109, p. 1-27 27 p., 103460.

  Research output › peer-review

  Open Access

• Coupled system thermal Hydraulics/CFD models: General guidelines and applications to heavy liquid metals

  Pucciarelli, A., Toti, A., Castelliti, D., Belloni, F., Van Tichelen, K., Moscardini, M., Galleni, F. & Forgione, N., Apr 2021, In: Annals of nuclear energy. 153, p. 1-23 23 p., 107990.

  Research output › peer-review

  Open Access

• Hunting for the correct pressure drop in a scaled reactor pool: Effect of geometry, mesh resolution, turbulence model and mass flow

  Lopes, S., Koloszar, L., Planquart, P., Visser, D. & Van Tichelen, K., 1 Dec 2021, In: Nuclear Engineering and Design. 384, p. 1-10 10 p., 111452.

  Research output › peer-review

  Open Access

• Liquid metal thermal hydraulics R&D at European scale: achievements and prospects

  Roelofs, F., Gerschenfeld, A. & Van Tichelen, K., 30 May 2021, In: Frontiers in Energy Research. 15, p. 842-853 12 p.

  Research output › peer-review

  Open Access
• 2020

  A collaborative effort towards the accurate prediction of turbulent flow and heat transfer in low-Prandtl number fluids

  Shams, A., Roelofs, F., Tiselj, I., Oder, J., Bartosiewicz, Y., Duponcheel, M., Niceno, B., Guo, W., Stalio, E., Angeli, D., Fregni, A., Buckingham, S., Koloszar, L., Villa Ortiz, A., Planquart, P., Narayanan, C., Lakehal, D., Van Tichelen, K., Jäger, W. & Schaub, T., 1 Sep 2020, In: Nuclear Engineering and Design. 366, p. 1-20 20 p., 110750.

  Research output › peer-review

  Open Access

• Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA

  Van Tichelen, K., Kennedy, G., Mirelli, F., Marino, A., Toti, A., Rozzia, D., Cascioli, E., Keijers, S. & Planquart, P., Feb 2020, In: Nuclear Technology. 206, 2, p. 150-163 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., 1 Mar 2020, In: Nuclear Engineering and Design. 358, 10 p., 110436.

  Research output › peer-review

  Open Access

• Experimental and numerical analysis of single pump failure in a HLM reactor

  Planquart, P. & Van Tichelen, K., Nov 2020, Transactions. 1 ed. American Nuclear Society, Vol. 123. p. 1523-1524 2 p. (Transactions of the American Nuclear Society).

  Research output › peer-review

• Experimental and Numerical Characterization of the Flow Field at the Core Entrance of a Water Model of a Heavy Liquid Metal–Cooled Reactor

  Planquart, P., Spaccapaniccia, C., Alessi, G., Buckingham, S. & Van Tichelen, K., Feb 2020, In: Nuclear Technology. 206, 2, p. 231-241 11 p.

  Research output › peer-review

  Open Access

• Numerical and experimental analysis of a planar jet with heated co-flow at medium and low Prandtl-number values

  Cascioli, E., Buckingham, S., Keijers, S., Van Tichelen, K. & Kenjeres, S., 18 Apr 2020, In: Nuclear Engineering and Design. 361, p. 1-11 11 p., 110570.

  Research output › peer-review

  Open Access

• Numerical simulation of Loss-of-Flow transient in the MYRRHA reactor

  Koloszar, L., Planquart, P., Van Tichelen, K. & Keijers, S., 1 Jul 2020, In: Nuclear Engineering and Design. 363, p. 1-11 11 p.

  Research output › peer-review

  Open Access

• Thermal-Hydraulic Experimental Testing of the MYRRHA Wire-Wrapped Fuel Assembly

  Kennedy, G., Van Tichelen, K., Pacio, J., Di Piazza, I. & Uitslag-Doolaard, H., Feb 2020, In: Nuclear Technology. 206, 2, p. 179-190 12 p.

  Research output › peer-review

  Open Access

• Validation of CFD analyses against pool experiments ESCAPE

  Visser, D., Roelofs, F., Mirelli, F. & Van Tichelen, K., Dec 2020, In: Nuclear Engineering and Design. 369, p. 1-7 7 p., 110864.

  Research output › peer-review

  Open Access
• 2019

  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 › peer-review

• 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 › peer-review

  Open Access

• 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

• Experimental investigation of accidental scenarios using a scale water model of a HLM reactor

  Planquart, P. & Van Tichelen, K., 18 Feb 2019, In: Nuclear Engineering and Design. 346, p. 10-16 7 p.

  Research output › peer-review

• 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 › peer-review