Photo of Timo Pättikangas

Timo Pättikangas

Principal Scientist, DSc (Tech)

1990 …2019
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Personal profile

Expertise area

Computational Fluid Dynamics (CFD), multiphase flows, modelling of industrial processes, nuclear reactor safety assessment

Fingerprint Dive into the research topics where Timo Pättikangas is active. These topic labels come from the works of this person. Together they form a unique fingerprint.

  • 13 Similar Profiles
Computational fluid dynamics Engineering & Materials Science
Fluid structure interaction Engineering & Materials Science
simulation Physics & Astronomy
charge flow devices Physics & Astronomy
Steam generators Engineering & Materials Science
Loss of coolant accidents Engineering & Materials Science
plasma waves Physics & Astronomy
Nucleate boiling Engineering & Materials Science

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Research Output 1990 2019

CFD simulations of direct-contact condensation of horizontal vapor jets

Pättikangas, T., Peltola, J., Hovi, V., Puustinen, M., Räsänen, A. & Kotro, E., 1 Jan 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019. cd-rom ed. American Nuclear Society ANS, p. 1583-1596 14 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

vapor jets
computational fluid dynamics
Contacts (fluid mechanics)
combustion stability
Condensation

Coupled APROS-CFD simulation of generic VVER-440 loss of feedwater transient

Rämä, T., Toppila, T., Kättö, J., Hovi, V. & Pättikangas, T., 1 Jan 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019. cd-rom ed. American Nuclear Society ANS, p. 5652-5666 15 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

charge flow devices
Computational fluid dynamics
Feedwater pumps
simulation
Trigger circuits

On development and validation of subcooled nucleate boiling models for openfoam foundation release

Peltola, J., Pättikangas, T., Bainbridge, W., Lehnigk, R. & Schlegel, F., 1 Jan 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019. cd-rom ed. American Nuclear Society ANS, p. 2149-2163 15 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

nucleate boiling
Nucleate boiling
heat transfer
bubbles
Heat transfer
3 Citations (Scopus)

Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage

Arkoma, A., Huhtanen, R., Leppänen, J., Peltola, J. & Pättikangas, T., 22 Apr 2018, In : Annals of Nuclear Energy. 119, p. 129–138 10 p.

Research output: Contribution to journalArticleScientificpeer-review

Spent fuels
Nuclear fuels
Computational fluid dynamics
Physics
Unloading

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 proceedingChapter or book articleProfessional

Open Access