Research output per year
Research output per year
Collaborations and top research areas from the last five years
Recent external collaboration on country/territory level. Dive into details by clicking on the dots or
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Development of a conservative safety demonstration for loss of forced flow events in MYRRHA
Hamidouche, T., Scheveneels, G. & Fernandez, R., Feb 2025, In: Annals of nuclear energy. 211, 13 p., 110981.Research output › peer-review
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The Belgian pre-licensing approach for MYRRHA
Sanda, I. G., Schyns, M. & Fernandez, R., 17 Dec 2024, Nuclear conference 2024: The 15th Biennial International Conference on Sustainable Development through Nuclear Research and Education. ICN Pitesti, p. 161-167 7 p.Research output › peer-review
Open Access -
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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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 -
Numerical analysis and codes qualification based on SIRIO experiments within the PIACE project
Lorusso, P., Tarantino, M., Nitti, F. S., Achilli, A., Cauzzi, M., Caramello, M., Hamidouche, T., Fernandez, R., Rozzia, D., Kljenak, I., Krpan, R., Jimenez, G., Queral, C. & Del Moro, T., 2023, Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. American Nuclear Society, p. 4851-4864 14 p. (Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023).Research output › peer-review