Research output per year
Research output per year
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Dive into the research topics where Juha Kyttälä is active. These topic labels come from the works of this person. Together they form a unique fingerprint.
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Research output
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Predicting sodium release in recovery boilers in conjunction with CFD furnace modelling
Jukola, P., Kyttälä, J. & McKeough, P., 2015, In: J-FOR: Journal of Science & Technology for Forest Products and Processes. 4, 4Research output: Contribution to journal › Article › Scientific › peer-review
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Predicting sodium release in recovery boilers in conjunction with CFD furnace modelling
Jukola, P., Kyttälä, J. & McKeough, P., 2014, 2014 International Chemical Recovery Conference. Nieminen, M. & Lampinen, P. (eds.). Vol. 2. p. 48-58Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
3 Citations (Scopus) -
Benchmark on hydrogen distribution in a containment based on the OECD-NEA THAI HM-2 experiment
Schwarz, S., Fischer, K., Bentaib, A., Burkhardt, J., Lee, J.-J., Duspiva, J., Visser, D., Kyttälä, J., Royl, P., Kim, J.-T., Kostka, P. & Liang, R., 2011, In: Nuclear Technology. 175, 3, p. 594-603 10 p.Research output: Contribution to journal › Article › Scientific › peer-review
38 Citations (Scopus) -
Benchmark on hydrogen distribution in a containment based on the OECD-NEA THAI HM-2 experiment
Schwarz, S., Fischer, K., Bentaib, A., Burkhardt, J., Lee, J.-J. ,. D. J., Visser, D., Kyttälä, J., Royl, P., Kim, J., Kostka, P. & Liang, R., 2009, Proceedings of the 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics. Atomic Energy Society of Japan, N13P1088Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
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FLUENT calculations of the hydrogen distribution in a containment during the OECD-NEA THAI HM-2 experiment
Visser, D. C., Komen, E. M. J., Houkema, M., Siccama, N. B., Kyttälä, J., Huhtanen, R. & Takasuo, E., 2009, Proceedings of the 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-13. Atomic Energy Society of Japan, N13P1159Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review