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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CFD simulation methodology for large-scale heavy liquid metal facility relevant for MYRRHA: Application to E-SCAPE facility
Lopes, S., Keijers, S., Koloszar, L., Pacio, J., Planquart, P. & Van Tichelen, K., Apr 2026, In: Nuclear Engineering and Design. 450, 18 p., 114798.Research output › peer-review
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Analyzing the effect of deformed pins in LMFR Rod Bundles
Roelofs, F., Dalvi, S., Uitslag-Doolaard, H. J., Daubner, M., Litfin, K., Profir, M., Moreau, V., Puviani, P. C., Martelli, D., Di Piazza, I., Ruiz González, J., Carbonelle, L., Fiore, M., Akkurt, M. C., Planquart, P. & Pacio, J., 1 Sep 2025, Proceedings of the 21st Internationa Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-21). American Nuclear Society, 14 p.Research output › peer-review
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Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages
Roelofs, F., Mathur, A., Uitslaag-Doolaard, H., Daubner, M., Liftin, K., Pacio, J. & Hassan, Y., 25 Aug 2025, In: Nuclear Technology. 15 p.Research output › peer-review
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Heavy liquid-metal pool thermal-hydraulic experiments and simulations
Van Tichelen, K., Keijers, S., Mirelli, F., Pacio, J., Serrano Diogo, R., Hussain, M. M. M. D., Pangukir, F. S. L., Visser, D., Roelofs, F., Koloszar, L., Lopes, S. & Planquart, P., 31 Aug 2025, NURETH-21 - 21st International Topical Meeting on Nuclear Reactor Thermal Hydrolics. Korean Nuclear Society, 24 p.Research output › peer-review
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How good is “good agreement” Considerations when comparing experiments with simulations for rod bundles with wire spacers
Pacio, J., Roelofs, F., Uitslag-Doolaard, H. J., Mathur, A., Schaver, D. R. & Merzari, E., 1 Sep 2025, 21st International Topical meeting on Nuclear Reactor Thermal Hydraulics: NURETH-21. Busan, Korea: American Nuclear Society, 14 p.Research output › peer-review