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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 Proceedings from the ERMSAR 2022 conference (p. 330 (14 pp.). SNETP.
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: 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
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
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
Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
Betschart, T., Lind, T., & Prasser, H. M. (2020). Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions. Nuclear Engineering and Design, 366, 110768 (14 pp.). https://doi.org/10.1016/j.nucengdes.2020.110768
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 1
Herranz, L. E., Pellegrini, M., Lind, T., Sonnenkalb, M., Godin-Jacqmin, L., López, C., … Sevon, T. (2020). 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 1. Nuclear Engineering and Design, 369, 110849 (7 pp.). https://doi.org/10.1016/j.nucengdes.2020.110849
Loss-of-cooling accident calculations for the wet storage pool of NPP Gösgen/Däniken
Jäckel, B. S., Steiner, P., & Klügel, J. U. (2020). Loss-of-cooling accident calculations for the wet storage pool of NPP Gösgen/Däniken. Nuclear Engineering and Design, 370, 110839 (6 pp.). https://doi.org/10.1016/j.nucengdes.2020.110839
Evaporation of materials from the molten salt reactor fuel under elevated temperatures
Kalilainen, J., Nichenko, S., & Krepel, J. (2020). Evaporation of materials from the molten salt reactor fuel under elevated temperatures. Journal of Nuclear Materials, 533, 152134 (13 pp.). https://doi.org/10.1016/j.jnucmat.2020.152134
A summary of fission-product-transport phenomena during SGTR severe accidents
Lind, T., Campbell, S., Herranz, L. E., Kissane, M., & Song, J. H. (2020). A summary of fission-product-transport phenomena during SGTR severe accidents. Nuclear Engineering and Design, 363, 110635 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110635
Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project
Nakayoshi, A., Rempe, J. L., Barrachin, M., Bottomley, D., Jacquemain, D., Journeau, C., … Song, J. H. (2020). Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project. Nuclear Engineering and Design, 369, 110857 (15 pp.). https://doi.org/10.1016/j.nucengdes.2020.110857
Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
Pellegrini, M., Herranz, L., Sonnenkalb, M., Lind, T., Maruyama, Y., Gauntt, R., … Mizokami, S. (2020). Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project. Nuclear Technology, 206(9), 1449-1463. https://doi.org/10.1080/00295450.2020.1724731
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 2
Sonnenkalb, M., Pellegrini, M., Herranz, L. E., Lind, T., Morreale, A. C., Kanda, K., … Sevon, T. (2020). 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 2. Nuclear Engineering and Design, 369, 110840 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110840
Statistical burnup distribution of moving pebbles in the HTR-PM reactor
Vitullo, F., Krepel, J., Kalilainen, J., Prasser, H. M., & Pautz, A. (2020). Statistical burnup distribution of moving pebbles in the HTR-PM reactor. Journal of Nuclear Engineering and Radiation Science, 6(2), 021108 (14 pp.). https://doi.org/10.1115/1.4044910