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Sami Penttilä

20062019
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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

Keywords

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

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Water Engineering & Materials Science
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Water cooled reactors Engineering & Materials Science
Oxidation resistance Engineering & Materials Science
Corrosion resistance Engineering & Materials Science
water Physics & Astronomy

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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. 51

Research 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