TAG 2.1 Thermal hydraulics and severe accidents
ALISA – Analytical and experimental investigation of severe accident phenomena, VTT
Research reports:
Sevón, T. 2023. Modelling steel oxidation in steam with MELCOR. VTT Research Report, VTT-R-00689-23. 29 p.
Pasi, A-E. 2023. Release of VOCs from painted surfaces. VTT Research Report, VTT-R-00840-23, 17 p.
CeReSa – CFD for Reactor Safety, VTT
Research reports:
Syrjänen, J., Niemi, T., Hovi, V. 2024. Validation of a CFD model for PWR containment analysis. VTT Research Report, VTT-R-00338-24. 38 p.
Peltonen, P., Niemi, T., Hovi, V. 2023. On modelling of turbulent dispersion in polydisperse flows. VTT Research Report, VTT-R-00808-23, 21 p.
Syrjänen, J., Hovi, V. 2023. Validation of a surface condensation model for PWR containment analysis. VTT Research Report, VTT-R-00884-23, 19 p.
Rämä, T. 2023. CeReSa subproject simulations of the selected Conan experiment with ANSYS fluent. Fortum report, 13 p.
C-FLOW – Critical Flow Separate-Effect-Test Facility & Experiments, LUT
Research reports:
Pyy, L., Kotro, E., Karppinen, J., Räsänen, A & Kouhia, V. 2023. General description of CRAFTY – first edition. Technical Report, LUT University, Nuclear Engineering. 28 p. + app. 35 p.
Theses:
Zaitsev, A. 2023. Modelling of two-phase critical flow in steam generator tube guillotine rupture scenario with Apros for the C-FLOW separate-effect-test facility. Master’s thesis, Lappeenranta-Lahti University of Technology LUT. 90 p. https://lutpub.lut.fi/handle/10024/166460
ESPO – Analysis of Passive Safety Systems’ Operations and Modelling, VTT
Research reports:
Alblouwy, F. 2024. Analysis of APSARA Test Facility Data with Apros and CATHARE-3 Codes. VTT Research Report, VTT-R-00068-24, 28 p.
GRAF – Gravity driven flow experiments, LUT
Conference papers and journal articles:
Hyvärinen, J., Riikonen, V., Telkkä, J., Hujala, E., Kouhia, V., Puustinen, M., Patel, G., Pyy, L., Vihavainen, J., Suikkanen, H., Rintala, V. 2024. Creating the foundation for safe nuclear power in Finland – Thermal hydraulics, safety analyses, safety justification methods research at the LUT University, 2000-2023. Nuclear Engineering and Design, Volume 419, April 2024. https://doi.org/10.1016/j.nucengdes.2024.112935
Riikonen, V., Telkkä, J., Kouhia, V., Puustinen, M., Giteshkumar, P., Pyy, L., Räsänen, A., Kotro, E., Hyvärinen, J., Murad, A. 2024. Helical coil steam generator stability experiments with the MOTEL test facility. Nuclear Engineering and Design, Volume 429, 1 December 2024, 113566. https://doi.org/10.1016/j.nucengdes.2024.113566
Telkkä, J., Riikonen, V., Kouhia, V., Puustinen, M., Pyy, L., Räsänen, A., Kotro, E., Hyvärinen, J. 2024. Experiments on open loop passive cooling of nuclear reactor containment: Quasi-steady-state heat removal, dynamic loads, and feasibility of practical periodic testing, Nuclear Engineering and Design, Volume 424, August 2024. https://doi.org/10.1016/j.nucengdes.2024.113317
Theses:
Toleukaiyr, T. 2023. Modelling of helical coil steam generator of MOTEL facility with Computational Fluid Dynamics (CFD) code. Master’s thesis, Lappeenranta-Lahti University of Technology LUT. 59 p. https://urn.fi/URN:NBN:fi-fe20231002138218
THEME – Computational Modeling of Thermal-Hydraulic Phenomena, VTT
