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

• 2024

  Analysis of the table top experiment run#8.1 by means of a systems thermal-hydraulic code

  Bakhit, A. & Potgieter, M. (Peer reviewer), 29 Aug 2024, 100 p.

  Research output

  Open Access

  File
  6 Downloads (Pure)

• 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

• Towards Early Detection of Model Conflicts in the Design of the MYRRHA Reactor in a Systems Engineering Approach

  De Florio, V., Greco, M., Kennedy, G., Brighenti, F., Potgieter, M., Makhov, K., Keijers, S., Lamberts, D. & Fernandez, R., 15 Dec 2024, In: Annals of nuclear energy. 209, 12 p., 110836.

  Research output › peer-review
• 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

• Fusion-dedicated material irradiation facilities at MYRRHA: Conceptual design and damage equivalence studies

  Terentyev, D., Leysen, W., Castin, N., Chang, C.-C., Kennedy, G., Stankovskiy, A. & Fiorito, L., Jun 2023, In: Fusion Engineering & Design. 191, 15 p., 113764.

  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

  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

• 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

• Comparison of lifetime assessments between ASME and RCC-MRx in liquid metal nuclear research reactors surfing from thermal striping

  Dougdag, M., Fernandez, R. & Lamberts, D., Nov 2022, In: Nuclear Engineering and Design. 398, 12 p., 111988.

  Research output › peer-review

  Open Access

• 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

• Determining the vibration frequencies of a pump for a high-density fluid

  Van Damme, M. & Makhov, K. (Peer reviewer), 28 Jun 2022, 97 p.

  Research output

  Open Access

  File
  6 Downloads (Pure)

• 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

• Risk reassessment of thermal striping due to a macro-crack pre-existent in nuclear reactors at high temperature

  Dougdag, M., Fernandez, R. & Lamberts, D., 1 Sep 2022, In: Annals of nuclear energy. 174, 11 p., 109152.

  Research output › peer-review

  Open Access

• Uncertainty margin for the maximum cladding temperature in the normal operation of MYRRHA

  Duchesne, C., Keijers, S. (Peer reviewer) & Pacio, J. (Peer reviewer), 23 Jun 2022, SCK CEN. 77 p.

  Research output

• 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

• Design evaluation of a scaled experiment to investigate natural circulation in MYRRHA

  Calabrese, D., Keijers, S. (Peer reviewer), Shin, Y.-H. (Peer reviewer) & Keijers, S. (Peer reviewer), 12 Mar 2021, 113 p.

  Research output

  Open Access

  File
  49 Downloads (Pure)

• MYRRHA – Multi-purpose hYbrid Research Reactor for High-tech Applications

  Romojaro, P., Fiorito, L., Stankovskiy, A., Van den Eynde, G., Fernandez, R., Kennedy, G., De Bruyn, D., Engelen, J., Vandeplassche, D. & Aït Abderrahim, H., 11 Nov 2021, In: SNE - Sociedad Nuclear Española - Technical Notes. p. 1-9 9 p., NT-01-21.

  Research output › peer-review

  Open Access
• 2020

  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

• 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

• Passive Shutdown Systems for Fast Neutron Reactors: Contribution to report

  Lamberts, D., 2020, Passive Shutdown Systems for Fast Neutron Reactors. 20 ed. IAEA - International Atomic Energy Agency, Vol. STI/PUB/1863. 110 p. (IAEA Nuclear Energy Series ; vol. 2020, no. NR-T-1.16 ).

  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., 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

• Conceptual design, activation and shielding of the 17 MeV beam dump

  Çelik, Y., Lamberts, D. & Beelen, Z., 12 Sep 2019, SCK CEN. 36 p. (SCK•CEN Reports; no. ER-0583)

  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 investigation of low-Prandtl triple jets

  Kaaks, B., Keijers, S. (Peer reviewer) & Van Tichelen, K. (Peer reviewer), 3 May 2019, 106 p.

  Research output

  Open Access

  File
  27 Downloads (Pure)

• 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

• Thermal Hydraulic Aspects of Liquid Metal Cooled Reactors

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

  Research output › peer-review

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

  Kennedy, G., Van Tichelen, K., Julio, P., Di Piazza, J. & Doolaard, H., 20 Jun 2019, In: Nuclear Technology. p. 1-12 12 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., Rohde, M., Pacio, J., Di Piazza, I., Kennedy, G., Van Tichelen, K., Obabko, A. & Merzari, E., 24 Aug 2019, In: Nuclear Engineering and Design. 353, 8 p., 110273.

  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

• 2018

  3.4 - Operational aspects of experimental liquid metal facilities

  Kennedy, G., Di Piazza, I. & Bassini, S., 5 Dec 2018, Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors. WP - Woodhead Publishing, p. 127-145 19 p.

  Research output › peer-review

  Open Access

• 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 › peer-review

  Open Access
• 2017

  Risk assessment of thermal striping in MYRRHA research reactor

  Dougdag, M., Fernandez, R. & Lamberts, D., 1 Aug 2017, In: Nuclear Engineering and Design. 319, p. 40-47 7 p.

  Research output › peer-review

  Open Access