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Dive into the research topics where Jari Lydman is active. These topic labels come from the works of this person. Together they form a unique fingerprint.
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Collaborations and top research areas from the last five years
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INCEFA-SCALE: INcreasing safety in NPPs by Covering gaps in Environmental Fatigue Assessment - focusing on gaps between laboratory data and component SCALE
Huotilainen, C., Seppänen, T., Que, Z., Ehrnstén, U. & Lydman, J.
1/10/20 → 30/09/25
Project: EU project
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ECC-SMART: Joint European Canadian Chinese development of Small Modular Reactor Technology
Toivonen, A., Penttilä, S., Peltonen, S., Lukin, J., Lydman, J., Väisänen, P., Arilahti, E. & Jäppinen, E.
1/09/20 → 31/08/24
Project: EU project
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INCEFA-PLUS: Increasing safety in NPPs by Covering gaps in Environmental Fatigue Assessment
Huotilainen, C., Seppänen, T., Que, Z., Lydman, J. & Ehrnstén, U.
1/07/15 → 31/10/20
Project: EU project
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Forum for the Effect of Thermal Aging and Microstructure on Mechanical and EAC Behaviour of Ni-base Alloy Dissimilar Metal Welds (FEMMA)
Que, Z., Lindqvist, S., Hytönen, N., Ge, Y., Nevasmaa, P., Lydman, J., Sirkiä, L., Arffman, P., Forsström, A. & Ehrnstén, U., 2023, VTT Technical Research Centre of Finland. 143 p. (VTT Technology; No. 420).Research output: Book/Report › Report
Open Access -
Mechanical behavior of high-Ni/high-Mn Barsebäck 2 reactor pressure vessel welds after 28 years of operation
Lindqvist, S., Norrgård, A., Arffman, P., Hytönen, N., Lydman, J., Efsing, P., Suman, S. & Nevasmaa, P., 1 Aug 2023, In: Journal of Nuclear Materials. 581, 154447.Research output: Contribution to journal › Article › Scientific › peer-review
Open AccessFile1 Citation (Scopus)4 Downloads (Pure) -
Brittle fracture initiation in decommissioned boiling water reactor pressure vessel head weld
Que, Z., Lindroos, M., Lydman, J., Hytönen, N., Lindqvist, S., Efsing, P., Nevasmaa, P. & Arffman, P., Oct 2022, In: Journal of Nuclear Materials. 569, 153925.Research output: Contribution to journal › Article › Scientific › peer-review
Open AccessFile5 Citations (Scopus)21 Downloads (Pure) -
BRUTE: Evaluation of Mechanical Properties of True Reactor Pressure Vessel Material From Barsebäck 2
Arffman, P., Lydman, J., Hytönen, N., Que, Z. & Lindqvist, S., 4 Nov 2022, ASME 2022 Pressure Vessels and Piping Conference: Materials and Fabrication. American Society of Mechanical Engineers (ASME), Vol. 4A. 7 p. PVP2022-83819Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
1 Citation (Scopus) -
Comparison of Weld Microstructure and Brittle Fracture Initiation of Reactor Pressure Vessel Head Weld and Beltline Axial Weld
Hytönen, N., Arffman, P., Lydman, J., Lindqvist, S., Que, Z. & Efsing, P., 2022, Fontevraud 10, September 19 to 22, 2022, Avignon, France. 8 p.Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review