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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
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
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
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).
Experimental investigation of hydrogen removal WITH Ag-zeolites under severe accident conditions
Mantzaras, J., Theile, J., Suckow, D., Lind, T., Espegren, F., Ishikawa, Y., … Kobayashi, S. (2022). Experimental investigation of hydrogen removal WITH Ag-zeolites under severe accident conditions. In 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19) (p. 35581 (14 pp.). American Nuclear Society.
First outcomes from the phebus FPT1 uncertainty application done in the EU-MUSA project
Mascari, F., Bersano, A., Massone, M., Agnello, G., Coindreau, O., Beck, S., … Sevon, T. (2022). First outcomes from the phebus FPT1 uncertainty application done in the EU-MUSA project. In 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19) (p. 35666 (16 pp.). American Nuclear Society.
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).
Experimental study of pool scrubbing related bubble hydrodynamics in the globule flow regime
Roth, B., Suckow, D., & Dehbi, A. (2022). Experimental study of pool scrubbing related bubble hydrodynamics in the globule flow regime. In 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19) (p. 35574 (15 pp.). American Nuclear Society.
Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release
Stuckert, J., Steinbrueck, M., Kalilainen, J., Lind, T., & Birchley, J. (2021). Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release. Nuclear Engineering and Design, 379, 111267 (11 pp.). https://doi.org/10.1016/j.nucengdes.2021.111267