Fingerprint Dive into the research topics where BA2506 Nuclear reactor materials is active. These topic labels come from the works of this organisation's members. Together they form a unique fingerprint.

Welds Engineering & Materials Science
Water Engineering & Materials Science
Stainless steel Engineering & Materials Science
Dissimilar metals Engineering & Materials Science
Fracture toughness Engineering & Materials Science
Stress corrosion cracking Engineering & Materials Science
Corrosion Engineering & Materials Science
Temperature Engineering & Materials Science

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No photo of Pentti Arffman

Pentti Arffman

Person: Research Scientists

No photo of Juha-Matti Autio

Juha-Matti Autio

Person: Research Scientists

Photo of Ulla Ehrnstén

Ulla Ehrnstén

Person: Senior Principal Scientists, Principal Scientists


Research Output 1984 2019

A crack-location correction for T 0 analysis of an alloy 52 dissimilar metal weld

Lindqvist, S., Ahonen, M., Lydman, J., Arffman, P. & Hänninen, H., 1 Jun 2019, In : Engineering Fracture Mechanics. 214, p. 320-334 15 p.

Research output: Contribution to journalArticleScientificpeer-review

Dissimilar metals
Fracture toughness
Fusion reactions

Effect of lead and applied potential on corrosion of carbon steel in steam generator crevice solutions

Bojinov, M., Jäppinen, E., Saario, T., Sipilä, K. & Toivonen, A., 24 Jul 2019, (Accepted/In press) In : Corrosion Science. 108117.

Research output: Contribution to journalArticleScientificpeer-review

Steam generators
Carbon steel
Stress corrosion cracking

Electrochemical investigation of in-service thermal aging in two CF8M cast stainless steels

Huotilainen, C., Ivanchenko, M., Efsing, P. & Ehrnsten, U., Jul 2019, In : Journal of Nuclear Materials. 520, p. 34-40 7 p.

Research output: Contribution to journalArticleScientificpeer-review

Thermal aging
Stainless Steel
stainless steels
Stainless steel