Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Jari Lydman"'
Autor:
Sebastian Lindqvist, Alex Norrgård, Pentti Arffman, Noora Hytönen, Jari Lydman, Pål Efsing, Siddharth Suman, Pekka Nevasmaa
Publikováno v:
Lindqvist, S, Norrgård, A, Arffman, P, Hytönen, N, Lydman, J, Efsing, P, Suman, S & Nevasmaa, P 2023, ' Mechanical behavior of high-Ni/high-Mn Barsebäck 2 reactor pressure vessel welds after 28 years of operation ', Journal of Nuclear Materials, vol. 581, 154447 . https://doi.org/10.1016/j.jnucmat.2023.154447
To assess long-term operation of the reactor pressure vessel (RPV), surveillance programs are applied for periodic monitoring and prediction of the aging of the mechanical properties due to irradiation and thermal embrittlement. In literature, there
Autor:
Zaiqing Que, Matti Lindroos, Jari Lydman, Noora Hytönen, Sebastian Lindqvist, Pål Efsing, Pekka Nevasmaa, Pentti Arffman
Publikováno v:
Que, Z, Lindroos, M, Lydman, J, Hytönen, N, Lindqvist, S, Efsing, P, Nevasmaa, P & Arffman, P 2022, ' Brittle fracture initiation in decommissioned boiling water reactor pressure vessel head weld ', Journal of Nuclear Materials, vol. 569, 153925 . https://doi.org/10.1016/j.jnucmat.2022.153925
The brittle fracture initiation behavior and fracture toughness in the ductile-to-brittle transition region for a thermally-aged weld metal of a decommissioned reactor pressure vessel head (in operation at 288 °C for 23 effective full power years) a
Autor:
Pål Efsing, Zai qing Que, Pekka Nevasmaa, Jari Lydman, Noora Hytönen, Ulla Ehrnstén, Pentti Arffman
Publikováno v:
Hytönen, N, Que, Z, Arffman, P, Lydman, J, Nevasmaa, P, Ehrnstén, U & Efsing, P 2021, ' Effect of weld microstructure on brittle fracture initiation in the thermally-aged boiling water reactor pressure vessel head weld metal ', International Journal of Minerals, Metallurgy and Materials, vol. 28, no. 5, pp. 867-876 . https://doi.org/10.1007/s12613-020-2226-6
Effects of the weld microstructure and inclusions on brittle fracture initiation are investigated in a thermally aged ferritic high-nickel weld of a reactor pressure vessel head from a decommissioned nuclear power plant. As-welded and reheated region
Publikováno v:
Que, Z, Huotilainen, C, Seppänen, T, Lydman, J & Ehrnstén, U 2022, ' Effect of machining on near surface microstructure and the observation of martensite at the fatigue crack tip in PWR environment of 304L stainless steel ', Journal of Nuclear Materials, vol. 558, 153399 . https://doi.org/10.1016/j.jnucmat.2021.153399
This work highlighted that a ground surface finish and the exposure to a pressurised water reactor (PWR) environment result in a decreased low-cycle fatigue lifetime, an enhanced fatigue crack initiation and an accelerated fatigue crack growth rate o
Publikováno v:
Lindqvist, S, Ahonen, M, Lydman, J, Arffman, P & Hänninen, H 2019, ' A crack-location correction for T 0 analysis of an alloy 52 dissimilar metal weld ', Engineering Fracture Mechanics, vol. 214, pp. 320-334 . https://doi.org/10.1016/j.engfracmech.2019.03.001
For narrow-gap Alloy 52 dissimilar metal welds, the fusion boundary between the ferritic pressure vessel steel and austenitic Ni-base alloy weld metal is the weakest region from fracture mechanical perspective. Producing of the pre-crack for fracture
Autor:
Matias Ahonen, Sebastian Lindqvist, Teemu Sarikka, Jari Lydman, Roman Mouginot, Ulla Ehrnstén, Pekka Nevasmaa, Hannu Hänninen
Publikováno v:
The Minerals, Metals & Materials Series ISBN: 9783030046385
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::14d99c6a2b9c2ac36bfb9fb8bcb0e4c6
https://doi.org/10.1007/978-3-030-04639-2_132
https://doi.org/10.1007/978-3-030-04639-2_132
Autor:
Hytönen, Noora, Que, Zai-qing, Arffman, Pentti, Lydman, Jari, Nevasmaa, Pekka, Ehrnstén, Ulla, Efsing, Pål
Publikováno v:
International Journal of Minerals, Metallurgy & Materials; May2021, Vol. 28 Issue 5, p867-876, 10p
This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange
This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange