Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Pentti Arffman"'
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
Autor:
Tomasz Brynk, Eberhard Altstadt, Pentti Arffman, Inge Uytdenhouwen, Marlies Lambrecht, Tom Petit
Publikováno v:
Brynk, T, Lambrecht, M, Uytdenhouwen, I, Arffman, P, Altstadt, E & Petit, T 2021, Fractesus project : General framework of materials selection and testing processes . in Proceedings of the ASME 2021 Pressure Vessels & Piping Conference : Materials and Fabrication . vol. 4, V004T06A066, American Society of Mechanical Engineers (ASME), ASME 2021 Pressure Vessels and Piping Conference, PVP 2021, Virtual, Online, 13/07/21 . https://doi.org/10.1115/PVP2021-61906
Volume 4: Materials and Fabrication
Volume 4: Materials and Fabrication
The H2020 project entitled “Fracture mechanics testing of irradiated RPV steels by means of sub-sized specimens (FRACTESUS)” started on the 1st October 2020. The aim of this project is to demonstrate the applicability of miniaturized compact tens
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6307b2a357f912c8c1b375e93d888641
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