Projektitutkija Joonas Telkkä

Mobile phone: +358 50 375 7765
Uploaded on: 29/10/2019

Current Organisation
Nuclear Safety Research Unit (Superior organisation: Laboratory of Energy Technology)

Research Interest
Experimental thermal hydraulics is needed to increase knowledge on functioning of nuclear power plants (NPP) and thus to enhance the safety of NPPs. Test facilities at LUT nuclear safety research laboratory are used either to ensure the functioning of safety systems of NPPs or to gain data for the validation of the computer codes. These codes are used to analyze the safety features of light water reactors. In the doctoral research advanced measurement techniques are used to acquire more information on thermal hydraulics of NPPs. Among these are particle image velocimetry (PIV) and wire mesh sensors (WMS).

Particle image velocimetry is a flow visualization technique, which allows for capturing velocity information of flow fields. PIV is based on illuminating of small tracer particles added to the flow with a laser apparatus. The movement of these illuminated particles is recorded with a camera system and converted into velocity information with a data acquisition system.

Wire mesh sensors are used to gain information on multiphase flows. WMS is based on the difference of multiphase flow phases regarding an electrical property, i.e. conductivity or permittivity/capacitance. WMS can be used to determine void fraction distributions, bubble size distributions and velocity distributions of multiphase flows.

Teaching Experience
Nuclear energy, nuclear power plant engineering, (experimental) thermal hydraulics.

Projects as Project Manager
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Development of Thermal-hydraulic Infrastructure at LUT (01/01/2016 - 31/03/2017)
Funder: Other Finnish

Projects as Co-Investigator
Advanced PTS Analysis for LTO (01/10/2020 - 30/09/2024)
Funder: European Commission

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PASI tests for VTT projects (2020)
Telkkä Joonas, Pyy Lauri, Riikonen Vesa
Defining void fraction with axial wire-mesh sensor in a swirling two-phase flow (2019)
A4 Conference proceedings
Telkkä Joonas, Jämsén Siiri, Hyvärinen Juhani
Specalists Workshop on Advanced Instrumentation and Measurement Techniques for Experiments related to Nuclear Reactor Thermal Hydraulics and Severe Accidents (SWINTH-2019)
General description of the PWR PACTEL test facility – fourth edition (2019)
Kouhia Virpi, Riikonen Vesa, Partanen Harri, et al.
Technical Report, PATE 1/2019
Integral and separate effects tests on thermal-hydraulic problems in reactors (INTEGRA) (2019)
D2 Article in a professional research book (incl. editor’s introduction)
Riikonen Vesa, Kouhia Virpi, Kauppinen Otso-Pekka, et al.
VTT Technology
SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018, Final Report
PASI - a test facility for research on passive heat removal (2019)
Kouhia Virpi, Riikonen Vesa, Kauppinen Otso-Pekka, et al.
PASI Natural Circulation Test NC-03 (2019)
Telkkä Joonas, Riikonen Vesa
PASI test plans (2019)
Riikonen Vesa, Purhonen Heikki, Kauppinen Otso-Pekka, et al.
General description of the PASI test facility, INTEGRA 1/2017, Research Report (2018)
Telkkä Joonas, Kouhia Virpi, Partanen Harri, et al.

Last updated on 2019-29-10 at 03:02