Research Output per year
Personal profile
Research interests
I am acting as a Research Team Leader in Nuclear Reactor Materials team. Our team is involved in mechanical testing of NPP components in hot cell environment, microstructural characterization by using state of the art electron microscopes, as well as different type of failure analyses on structural materials. My own expertise is related to high temperature oxidation of structural materials, like ATF claddings. I'm also familiar with different future type of reactors like GenIV and their material solutions. I'm taking actively part in different international forums/working groups like EERA JPNM (SC member), GIF & IAEA.
Education/Academic qualification
Manufacturing and processing, Master
Keywords
- Q Science (General)
- high temperature
- oxidation resistance
- cladding
Fingerprint Dive into the research topics where Sami Penttilä is active. These topic labels come from the works of this person. Together they form a unique fingerprint.
- 32 Similar Profiles
Water
Engineering & Materials Science
Oxidation
Engineering & Materials Science
Corrosion
Engineering & Materials Science
Austenitic stainless steel
Engineering & Materials Science
Water cooled reactors
Engineering & Materials Science
Oxidation resistance
Engineering & Materials Science
Corrosion resistance
Engineering & Materials Science
water
Physics & Astronomy
Network
Recent external collaboration on country level. Dive into details by clicking on the dots.
Research Output 2006 2019
Performance of aluminide and cr-modified aluminide pack cementation-coated stainless steel 304 in supercritical water at 700 °c
Tepylo, N., Huang, X., Jiang, S. & Penttilä, S., 2019, In : Journal of Nuclear Engineering and Radiation Science. 5, 1, 011014.Research output: Contribution to journal › Article › Scientific › peer-review
cementation
stainless steels
Stainless steel
water
Water
1
Citation
(Scopus)
Miniature Autoclave and Double Bellows Loading Device for Material Testing in Future Reactor Concept Conditions: Case Supercritical Water
Penttilä, S., Moilanen, P., Karlsen, W. & Toivonen, A., 1 Jan 2018, In : Journal of Nuclear Engineering and Radiation Science. 4, 1, 021006.Research output: Contribution to journal › Article › Scientific › peer-review
Open Access
bellows
Bellows
autoclaves
Materials testing
Autoclaves
Overview of oxidation tests results of austenitic alloys coated by CrN and NiCrAlY in high temperature steam environments
Penttilä, S., Toivonen, A., Peltonen, S. & Huang, X., 31 Dec 2018, Proceedings of 1st International Conference on Generation IV and Small Reactors. Rouben, B. (ed.). p. 1-12 12 p. 51Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
Steam
Oxidation
Temperature
Zirconium
Accidents
5
Citations
(Scopus)
Oxidation Behaviour of Alloys 800H, 3033 and 304 in High-Temperature Supercritical Water
Bsat, S., Xiao, B., Huang, X. & Penttilä, S., 2018, In : Oxidation of Metals. 89, 1-2, p. 151-163 13 p.Research output: Contribution to journal › Article › Scientific › peer-review
Oxidation
Water
Temperature
Water cooled reactors
Energy dispersive spectroscopy
Condition monitoring, thermal and radiation degradation of polymers inside NPP containments (COMRADE)
Sipilä, K., Joki, H., Lavonen, T., Paajanen, A., Penttilä, S., Granlund, M., Bondesson, A. & Jansson, A., 2017, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Interim Report. VTT Technical Research Centre of Finland, p. 274-285 (VTT Technology, Vol. 294).Research output: Chapter in Book/Report/Conference proceeding › Chapter or book article › Professional
Open Access