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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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
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Test matrices definition for the SIRIO facility in the frame of the H2020-PIACE project: Pre-test simulation and conclusions
Hamidouche, T., Fernandez, R., Gianetti, F., Narcisi, V., Molinari, M., Achilli, A., Queral, C., Lorusso, P., Mazzi, D., Nitulescu, L., Caramello, M., Frignani, M., Tarantino, M., Jimenez, G., Kljenak, I. & Oder, J., 30 Sep 2022, Technical meeting on State-of-the-art Thermal Hydraulics of Fast Reactors. IAEA - International Atomic Energy Agency, 11 p.Research output › peer-review
Open Access -
Total loss of flow benchmark in CIRCE-HERO integral test facility
Lorusso, P., Del Nevo, A., Narsisi, V., Giannetti, F., Caruso, G., Zwijssen, K., Breijder, P. A., Hamidouche, T., Castelliti, D., Rozzia, D. & Tarantino, M., 1 May 2021, In: Nuclear Engineering and Design. 376, p. 1-24 24 p., 111086.Research output › peer-review
Open Access -
H2020 MYRTE CIRCE-HERO experimental campaign: Post-test activity and code validation
Castelliti, D., Hamidouche, T., Lorusso, P. & Tarantino, M., Aug 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18). American Nuclear Society, p. 5029-5042 14 p.Research output