| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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). |
| 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 |
| Uncertainty quantification study on gas phase iodine release from Fukushima Daiichi accident in unit 3
Kalilainen, J., & Lind, T. (2022). Uncertainty quantification study on gas phase iodine release from Fukushima Daiichi accident in unit 3. Annals of Nuclear Energy, 166, 108740 (13 pp.). https://doi.org/10.1016/j.anucene.2021.108740 |
| MSR simulation with cGEMS: salt and fission product evaporation
Lind, T., Kalilainen, J., & Nichenko, S. (2022). MSR simulation with cGEMS: salt and fission product evaporation. 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. 272 (12 pp.). Karlsruher Institut für Technologie (KIT). |
| The parametric sensitivity analysis of FPT-1 MELCOR 2.2 input deck as a preparation for uncertainty quantification study
Malicki, M., Lind, T., & Kalilainen, J. (2022). The parametric sensitivity analysis of FPT-1 MELCOR 2.2 input deck as a preparation for uncertainty quantification study. 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. 274 (14 pp.). Karlsruher Institut für Technologie (KIT). |
| MSR simulation with cGEMS: fission product release and aerosol formation
Nichenko, S., Kalilainen, J., & Lind, T. (2022). MSR simulation with cGEMS: fission product release and aerosol formation. Journal of Nuclear Engineering, 3(1), 105-116. https://doi.org/10.3390/jne3010006 |
| Current understanding of high-temperature oxidation phenomena during air ingress scenarios
Park, S., Lind, T., Birchley, J., & Steinbrueck, M. (2022). Current understanding of high-temperature oxidation phenomena during air ingress scenarios. 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. 284 (10 pp.). Karlsruher Institut für Technologie (KIT). |
| Droplet size distribution in a full-scale rectangular self-priming Venturi scrubber with liquid film injection
Breitenmoser, D., Papadopoulos, P., Lind, T., & Prasser, H. M. (2021). Droplet size distribution in a full-scale rectangular self-priming Venturi scrubber with liquid film injection. International Journal of Multiphase Flow, 142, 103694 (15 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2021.103694 |
| Experimental investigation on bubble behaviors in a water pool using the venturi scrubbing nozzle
Choi, Y. J., Kam, D. H., Padopoulos, P., Lind, T., & Jeong, Y. H. (2021). Experimental investigation on bubble behaviors in a water pool using the venturi scrubbing nozzle. Nuclear Engineering and Technology, 53, 1756-1768. https://doi.org/10.1016/j.net.2020.11.024 |
| Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3
Lind, T., Pellegrini, M., Herranz, L. E., Sonnenkalb, M., Nishi, Y., Tamaki, H., … Sevon, T. (2021). Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3. Nuclear Engineering and Design, 376, 111138 (12 pp.). https://doi.org/10.1016/j.nucengdes.2021.111138 |
| Modelling of fission products release in VERDON-1 experiment with cGEMS: coupling of severe accident code MELCOR with GEMS thermodynamic modelling package
Nichenko, S., Kalilainen, J., Fernandez Moguel, L., & Lind, T. (2021). Modelling of fission products release in VERDON-1 experiment with cGEMS: coupling of severe accident code MELCOR with GEMS thermodynamic modelling package. Annals of Nuclear Energy, 152, 107972 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107972 |
| Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM
Skolik, K., Allison, C., Hohorst, J., Malicki, M., Perez-Ferragut, M., Pieńkowski, L., & Trivedi, A. (2021). Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM. Progress in Nuclear Energy, 134, 103648 (15 pp.). https://doi.org/10.1016/j.pnucene.2021.103648 |
