| 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 |
| 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 |
| 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). |
| 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. |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| The influence of thermal radiation on the free convection inside enclosures
Dehbi, A., Kelm, S., Kalilainen, J., & Mueller, H. (2019). The influence of thermal radiation on the free convection inside enclosures. Nuclear Engineering and Design, 341, 176-185. https://doi.org/10.1016/j.nucengdes.2018.10.025 |
| Aerosol results of the QUENCH-18 bundle test
Kalilainen, J., Lind, T., Stuckert, J., & Stegmaier, U. (2019). Aerosol results of the QUENCH-18 bundle test. In Proceedings of the ERMSAR 2019 (p. 019 (11 pp.). sine nomine. |
| The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test
Kalilainen, J., Lind, T., Stuckert, J., Bergfeldt, T., Sippula, O., & Jokiniemi, J. (2019). The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test. Journal of Nuclear Materials, 517, 315-327. https://doi.org/10.1016/j.jnucmat.2019.02.021 |
| Contribution to the understanding of iodine transport under primary circuit conditions: Csi/Cd and Csi/Ag interactions in condensed phase
Gouëllo, M., Kalilainen, J., Kärkelä, T., & Auvinen, A. (2018). Contribution to the understanding of iodine transport under primary circuit conditions: Csi/Cd and Csi/Ag interactions in condensed phase. Nuclear Materials and Energy, 17, 259-268. https://doi.org/10.1016/j.nme.2018.11.011 |
| Aerosol depletion in natural circulation in simplified geometry
Kalilainen, J., Kim, H., Dehbi, A., & Lind, T. (2018). Aerosol depletion in natural circulation in simplified geometry. In Vol. 1. International congress on advances in nuclear power plants (ICAPP 2018) (pp. 571-577). American Nuclear Society. |
| Loss of forced cooling accident analysis of HTR-PM using MELCOR 2.2 code
Kalilainen, J., Lind, T., & Prasser, H. M. (2018). Loss of forced cooling accident analysis of HTR-PM using MELCOR 2.2 code. In Proceedings of HTR 2018 (p. (7 pp.). sine nomine. |
| Measurements and LES computations of a turbulent particle-laden flow inside a cubical differentially heated cavity
Kim, H., Dehbi, A., & Kalilainen, J. (2018). Measurements and LES computations of a turbulent particle-laden flow inside a cubical differentially heated cavity. Atmospheric Environment, 186, 216-228. https://doi.org/10.1016/j.atmosenv.2018.05.037 |
| Statistical burnup distribution of moving pebbles in HTR-PM reactor
Vitullo, F., Krepel, J., Kalilainen, J., Prasser, H. M., & Pautz, A. (2018). Statistical burnup distribution of moving pebbles in HTR-PM reactor. In Proceedings of the 26th international conference on nuclear engineering (ICONE26). Student Paper Competition (pp. ICONE26-81082 (10 pp.). https://doi.org/10.1115/ICONE26-81082 |
| A large eddy simulation of turbulent particle-laden flow inside a cubical differentially heated cavity
Dehbi, A., Kalilainen, J., Lind, T., & Auvinen, A. (2017). A large eddy simulation of turbulent particle-laden flow inside a cubical differentially heated cavity. Journal of Aerosol Science, 103, 67-82. https://doi.org/10.1016/j.jaerosci.2016.10.003 |
