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Pekka Moilanen

19972018
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  • 14 Similar Profiles
Fatigue of materials Engineering & Materials Science
Creep Engineering & Materials Science
Pneumatics Engineering & Materials Science
Testing Engineering & Materials Science
Superalloys Engineering & Materials Science
Nickel Engineering & Materials Science
Materials testing Engineering & Materials Science
Creep testing Engineering & Materials Science

Research Output 1997 2018

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

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., 2017, p. 328-343.

Research output: Contribution to conference › Conference article › Scientific › peer-review

Creep performance of fuel cladding

Pohja, R., Tulkki, V., Ikonen, T., Moilanen, P., Rantala, J., Huotilainen, S. & Ehrnstén, U., 2016, Baltica X: International Conference on Life Management and Maintenance for Power Plants. Auerkari, P. (ed.). Espoo: VTT Technical Research Centre of Finland, 8 p. (VTT Technology, Vol. 261).

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

Open Access
Creep
Zirconium alloys
Nuclear fuel cladding
Nuclear reactors
Austenitic stainless steel

Multiaxial creep testing device for nuclear fuel claddings

Pohja, R., Moilanen, P., Rantala, J., Huotilainen, S., Tulkki, V., Ehrnstén, U. & Holmström, S., 2016, In : Athens Journal of Sciences. 3, 3, p. 227-240

Research output: Contribution to journal › Article › Scientific › peer-review

Open Access
Nuclear fuel cladding
Creep testing
Creep
Pneumatics
Nuclear reactors

Water purification system for the Electric Discharge Machine (EDM)

Moilanen, P., Paasila, M. & Lappalainen, P., 2016, VTT Technical Research Centre of Finland. 36 p. (VTT Research Report, Vol. VTT-R-05845-15).

Research output: Book/Report › Report › Professional