Research output per year
Research output per year
- 16 results
Search results
-
2024
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
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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
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2023
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 -
2022
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 -
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 -
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 -
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
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 -
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 -
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 -
2018
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