Sami Penttilä

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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


  • Q Science (General)
  • high temperature
  • oxidation resistance
  • cladding

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Water Engineering & Materials Science
Oxidation Engineering & Materials Science
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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

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Projects 2019 2019

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 journalArticleScientificpeer-review

stainless steels
Stainless steel
1 Citation (Scopus)
Open Access
Materials testing

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. 51

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

6 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 journalArticleScientificpeer-review

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 proceedingChapter or book articleProfessional

Open Access