| Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project
Mascari, F., Bersano, A., Massone, M., Agnello, G., Coindreau, O., Beck, S., … Sevon, T. (2024). Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project. Annals of Nuclear Energy, 196, 110205 (14 pp.). https://doi.org/10.1016/j.anucene.2023.110205 |
| Two-phase hydrodynamics and aerosol mass transfer characterization in pool scrubbing: a simultaneous measurement technique
Ramos Perez, A., Lind, T., Petrov, V., Manera, A., & Prasser, H. M. (2024). Two-phase hydrodynamics and aerosol mass transfer characterization in pool scrubbing: a simultaneous measurement technique. Journal of Aerosol Science, 178, 106336 (17 pp.). https://doi.org/10.1016/j.jaerosci.2024.106336 |
| Experimental study for high Reynolds’ gas-liquid two-phase flow through rod bundle using Wire Mesh Sensor (WMS)
Al-Yahia, O. S., Clifford, I., Bissels, W. M., Suckow, D., & Ferroukhi, H. (2023). Experimental study for high Reynolds’ gas-liquid two-phase flow through rod bundle using Wire Mesh Sensor (WMS). Nuclear Engineering and Design, 405, 112224 (23 pp.). https://doi.org/10.1016/j.nucengdes.2023.112224 |
| Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes
Coindreau, O., Herranz, L. E., Bocanegra, R., Ederli, S., Maccari, P., Mascari, F., … Nudi, M. (2023). Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes. Annals of Nuclear Energy, 188, 109796 (9 pp.). https://doi.org/10.1016/j.anucene.2023.109796 |
| Methyl iodide retention in Ag-Zeolite material under filtered containment venting system condition
Espegren, F., Suckow, D., Lind, T., Mantzaras, J., & Theile, J. (2023). Methyl iodide retention in Ag-Zeolite material under filtered containment venting system condition. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 3759-3771). https://doi.org/10.13182/NURETH20-40735 |
| Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – overview and first results
Gupta, S., Herranz, L. E., Lebel, L. S., Sonnenkalb, M., Pellegrini, M., Marchetto, C., … Kärkelä, T. (2023). Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – overview and first results. Nuclear Engineering and Design, 404, 112189 (20 pp.). https://doi.org/10.1016/j.nucengdes.2023.112189 |
| Advanced FCVS system using silver zeolite AgX, AgR and XeA
Ishikawa, Y., Endo, K., Narabayashi, T., Suckow, D., Espegren, F., Lind, T., … Kawahara, Y. (2023). Advanced FCVS system using silver zeolite AgX, AgR and XeA. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 4248-4255). https://doi.org/10.13182/NURETH20-40634 |
| Advanced radioactive material removal system using silver zeolite (3) filtered containment venting system (FCVS) hydrogen measures
Ishikawa, Y., Endo, K., Kobayashi, T., Narabayashi, T., Kawahara, Y., & Suckow, D. J. (2023). Advanced radioactive material removal system using silver zeolite (3) filtered containment venting system (FCVS) hydrogen measures. In Vol. 30. Proceedings of the 2023 30th international conference on nuclear engineering ICONE30 (pp. 1-3). https://doi.org/10.1299/jsmeicone.2023.30.1620 |
| Nitriding model for zirconium based fuel cladding in severe accident codes
Jäckel, B. S., Birchley, J. C., Lind, T., Steinbrück, M., & Park, S. (2023). Nitriding model for zirconium based fuel cladding in severe accident codes. Journal of Nuclear Materials, 582, 154466 (7 pp.). https://doi.org/10.1016/j.jnucmat.2023.154466 |
| OECD/NEA ARC-F project: summary of fission product transport
Lind, T., Kalilainen, J., Marchetto, C., Beck, S., Nakamura, K., Kino, C., … Dolganov, K. (2023). OECD/NEA ARC-F project: summary of fission product transport. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 4796-4809). https://doi.org/10.13182/NURETH20-40120 |
| Impact of PSI-KIT nitriding model on hypothetical spent fuel pool accident simulation
Malicki, M., & Lind, T. (2023). Impact of PSI-KIT nitriding model on hypothetical spent fuel pool accident simulation. Nuclear Engineering and Technology, 55(7), 2504-2515. https://doi.org/10.1016/j.net.2023.04.003 |
| Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1
Malicki, M., & Lind, T. (2023). Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1. Progress in Nuclear Energy, 158, 104609 (15 pp.). https://doi.org/10.1016/j.pnucene.2023.104609 |
| The iPWR MELCOR 2.2 parametric sensitivity analysis
Malicki, M., Darnowski, P., & Lind, T. (2023). The iPWR MELCOR 2.2 parametric sensitivity analysis. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 4220-4233). https://doi.org/10.13182/NURETH20-40213 |
| Recombination of hydrogen and carbon monoxide on silver-based zeolites in the presence of steam and at pressures up to 3 bar
Mantzaras, J., Arumugan, V. K., Theile, J., Suckow, D., Espegren, F., & Lind, T. (2023). Recombination of hydrogen and carbon monoxide on silver-based zeolites in the presence of steam and at pressures up to 3 bar. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 4020-4033). https://doi.org/10.13182/NURETH20-40692 |
| Current status of MELCOR 2.2 for fusion safety analyses
Mascari, F., Bersano, A., Adorni, M., D'Ovidio, G., Martín-Fuertes, F., Jin, X. Z., … Malicki, M. (2023). Current status of MELCOR 2.2 for fusion safety analyses. Fusion Engineering and Design, 194, 113869 (7 pp.). https://doi.org/10.1016/j.fusengdes.2023.113869 |
| Measurement of aerosol mass transfer and hydrodynamics in a bubble column using Wire-Mesh sensors
Ramos Perez, A., Lind, T., Manera, A., Petrov, V., & Prasser, H. M. (2023). Measurement of aerosol mass transfer and hydrodynamics in a bubble column using Wire-Mesh sensors. In 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20) (pp. 2402-2415). https://doi.org/10.13182/NURETH20-40223 |
| MELCOR 2.2-ASTEC V2.2 crosswalk study reproducing SBLOCA and CSBO scenarios in a PWR1000-like reactor part I: analysis of RCS thermal-hydraulics and in-vessel phenomena
Di Giuli, M., Malicki, M., Dejardin, P., Corda, V., & Swaidan, A. M. (2022). MELCOR 2.2-ASTEC V2.2 crosswalk study reproducing SBLOCA and CSBO scenarios in a PWR1000-like reactor part I: analysis of RCS thermal-hydraulics and in-vessel phenomena. Nuclear Engineering and Design, 387, 111248 (22 pp.). https://doi.org/10.1016/j.nucengdes.2021.111248 |
| Effectiveness of hydrogen recombination by AgX and AgR zeolites
Espegren, F., Suckow, D., Lind, T., Mantzaras, J., Theile, J., Ishikawa, Y., … Kobayashi, S. (2022). Effectiveness of hydrogen recombination by AgX and AgR zeolites. In F. Gabrielli, L. E. Herranz, & S. Paci (Eds.), Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident (p. 330 (14 pp.). Karlsruher Institut für Technologie (KIT). |
| Integration of pool scrubbing research to enhance source-term calculations (IPRESCA) project
Gupta, S., Herranz, L. E., Lebel, L. S., Sonnenkalb, M., Pellegrini, M., Marchetto, C., … Kärkelä, T. (2022). Integration of pool scrubbing research to enhance source-term calculations (IPRESCA) project. In 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19) (p. 33970 (16 pp.). American Nuclear Society. |
| The use of a novel gradient heat flux sensor for characterization of reflux condensation
Janasz, F., Prasser, H. M., Suckow, D., & Mityakov, A. (2022). The use of a novel gradient heat flux sensor for characterization of reflux condensation. Nuclear Engineering and Design, 395, 111885 (9 pp.). https://doi.org/10.1016/j.nucengdes.2022.111885 |
