Research Output per year
Fingerprint Dive into the research topics where Ismo Karppinen is active. These topic labels come from the works of this person. Together they form a unique fingerprint.
- 28 Similar Profiles
Computational fluid dynamics
Engineering & Materials Science
Loss of coolant accidents
Engineering & Materials Science
Fluid structure interaction
Engineering & Materials Science
Hydraulics
Engineering & Materials Science
loss of coolant
Physics & Astronomy
fluid-structure interaction
Earth & Environmental Sciences
Nuclear reactors
Engineering & Materials Science
Pressure vessels
Engineering & Materials Science
Network
Recent external collaboration on country level. Dive into details by clicking on the dots.
Research Output 1999 2019
Critical flow prediction by system codes - Recent analyses made within the FONESYS network
Lanfredini, M., Bestion, D., D'Auria, F., Aksan, N., Fillion, P., Gaillard, P., Heo, J., Karppinen, I., Kim, K. D., Kurki, J., Lifang, L., Shen, A., Vacher, J. L. & Wang, D., 1 Jan 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 20192019. American Nuclear Society ANS, p. 2274-2287 14 p.Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
critical flow
hydraulics
Hydraulics
predictions
Nuclear reactors
Comprehensive and systematic validation of independent safety analysis tools (COVA)
Hillberg, S., Karppinen, I., Silde, A., Kolehmainen, J., Dorval, E., Leskinen, J., Kurki, J., Alku, T., Lauerma, S., Skripnikov, D. & Hovi, T., 2017, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Interim Report. VTT Technical Research Centre of Finland, p. 215-222 (VTT Technology, Vol. 294).Research output: Chapter in Book/Report/Conference proceeding › Chapter or book article › Professional
Open Access
Development and validation of CFD methods for nuclear reactor safety assessment (NURESA)
Pättikangas, T., Ala-Juusela, J., Hovi, V., Huhtanen, R., Karppinen, I., Leskinen, J., Patel, G., Peltola, J., Rämä, T., Siikonen, T., Tanskanen, V. & Toppila, T., 2017, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Interim Report. VTT Technical Research Centre of Finland, p. 253-265 (VTT Technology, Vol. 294).Research output: Chapter in Book/Report/Conference proceeding › Chapter or book article › Professional
Open Access
Integrated transient simulation of a BFB boiler with CFD models for the BFB furnace and dynamic system models for the steam cycle and boiler operation
Hovi, V., Huttunen, M., Karppinen, I., Pättikangas, T., Niemistö, H., Karvonen, L., Kallio, S., Tuuri, S. & Ylä-Outinen, V., 1 Jan 2017, In : Energy Procedia. 120, August, p. 508-515 8 p.Research output: Contribution to journal › Article › Scientific › peer-review
Open Access
Boilers
Computational fluid dynamics
Dynamical systems
Furnaces
Steam
8
Citations
(Scopus)
Benchmark exercise on SBLOCA experiment of PWR PACTEL facility
Kouhia, V., Riikonen, V., Kauppinen, O-P., Purhonen, H., Austregesilo, H., Bánáti, J., Cherubini, M., D'Auria, F., Inkinen, P., Karppinen, I., Kral, P., Peltokorpi, L., Peltonen, J. & Weber, S., 2013, In : Annals of Nuclear Energy. 59, p. 149-156 7 p.Research output: Contribution to journal › Article › Scientific › peer-review
Experiments
Loss of coolant accidents
Launching
Heat losses
Coolants