Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Lappalainen, Petteri"'
Autor:
Sánchez, Marcos, Cicero, Sergio, Arroyo, Borja, Bonny, Giovanni, Swan, Helen, Lappalainen, Petteri, Altstadt, Eberhard, Petit, Tom, Obermeier, Florian
Publikováno v:
In Procedia Structural Integrity 2023 47:22-29
Publikováno v:
Seppänen, T, Lindqvist, S, Arffman, P & Lappalainen, P 2023, Embrittlement Trend Curves and Reactor Pressure Vessel Operation in Finland . in W L Server, M Brumovský & M Kirk (eds), Radiation Embrittlement Trend Curves and Equations and Their Use for RPV Integrity Evaluations . American Society for Testing and Materials (ASTM), pp. 259-283, ASTM Symposium on Radiation Embrittlement Trend Curves/Equations and Their Use for RPV Integrity Evaluations, Prague, Czech Republic, 19/04/23 . https://doi.org/10.1520/STP164720220038
To evaluate embrittlement from neutron irradiation, Finnish regulations have required the use of surveillance programs in light water reactors since the 1970s. These are applied in the five operating reactors: two VVER-440s at Loviisa (LO1 and LO2),
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::a8926ff5f34ab55822bde039743d33e6
https://cris.vtt.fi/en/publications/42cea55c-193e-42c0-acb0-898b5fc0567b
https://cris.vtt.fi/en/publications/42cea55c-193e-42c0-acb0-898b5fc0567b
Autor:
Huotilainen, Caitlin, Que, Zaiqing, Ge, Yanling, Lappalainen, Petteri, Hytönen, Noora, Korhonen, Ritva, Huotilainen, Santtu, Kytömöki, Petri
Publikováno v:
Huotilainen, C, Que, Z, Ge, Y, Lappalainen, P, Hytönen, N, Korhonen, R, Huotilainen, S & Kytömöki, P 2022, Effect Of Thermal Aging On The Microstructure And Mechanical Properties Of High-Ni And Ni-Base Alloys . in AMPP Conference Papers . Association for Materials Protection and Performance, AMPP, 20th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, Snowmass, Colorado, United States, 17/07/22 .
The long-term exposure of metallic structures, systems and components to power plant operating temperatures can lead to thermal aging and subsequent degradation. In a VVER-type pressurized water reactor, high-nickel alloys are used in some high-stren
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::ea87b85f1d3849b6b7dcdaf8b49808ac
https://cris.vtt.fi/en/publications/12479ffe-71b2-47fe-915a-89d41fd257c3
https://cris.vtt.fi/en/publications/12479ffe-71b2-47fe-915a-89d41fd257c3
Publikováno v:
Rinta-aho, J, Lappalainen, P & Leskelä, E 2019, Non-destructive evaluation of material degradation of nuclear reactor pressure vessels . in Baltica XI : International Conference on Life Management and Maintenance for Power Plants . VTT Technical Research Centre of Finland, Baltica XI 2019, Helsinki, Finland, 11/06/19 .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::e38246119872b35b0300af061ba5dc46
https://cris.vtt.fi/ws/files/27466053/S6_Rinta_aho_etal.pdf
https://cris.vtt.fi/ws/files/27466053/S6_Rinta_aho_etal.pdf
Autor:
Valo, Matti, Lappalainen, Petteri
Publikováno v:
Valo, M & Lappalainen, P 2015, Electrical resistivity response to annealing of VVER440-type weld material in irradiated, post-irradiation annealed and re-irradiated conditions . VTT Research Report, vol. VTT-R-00163-15, VTT Technical Research Centre of Finland .
In the work resistivity response to annealing of weld 501 materials in various irradiationannealing-reirradiation conditions was measured by using isothermal annealing. Annealing temperature of 420°C was chosen in order to get relatively slow anneal
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::e612049ef002ca5b04d6b3f82151a6ed
https://cris.vtt.fi/en/publications/b022d5da-e31d-4cce-9d94-78bec4abbf54
https://cris.vtt.fi/en/publications/b022d5da-e31d-4cce-9d94-78bec4abbf54
Publikováno v:
Pulkkanen, V-M, Lappalainen, P & Valo, M 2015, Modelling heat transfer in electron beam welding . Helsinki University of Technology: Systems Analysis Laboratory. A: Research Reports, vol. VTT-R-00368-15, VTT Technical Research Centre of Finland .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::62bc37928f2194cb7a53a5f1609decd3
https://cris.vtt.fi/en/publications/552743ad-8a62-412b-9d02-90397dbeafec
https://cris.vtt.fi/en/publications/552743ad-8a62-412b-9d02-90397dbeafec
Publikováno v:
Lappalainen, P, Talja, R & Valo, M 2015, Validation of melting temperatures of temperature monitoring alloys by DSC . VTT Research Report, vol. VTT-R-00162-15, VTT Technical Research Centre of Finland .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::871716c39755af996746c5faf880be4d
https://cris.vtt.fi/en/publications/d4fdaa51-7b2b-447e-b103-f639cdba1712
https://cris.vtt.fi/en/publications/d4fdaa51-7b2b-447e-b103-f639cdba1712
Publikováno v:
Valo, M, Ehrnsten, U, Planman, T, Lappalainen, P & Wallin, K 2014, Supplementary tests with CRIEPI mini CT-specimens . Helsinki University of Technology: Systems Analysis Laboratory. A: Research Reports, no. VTT-R-05628-14, VTT Technical Research Centre of Finland .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::7ce34d6b889f2ef59ed79572642fd066
https://cris.vtt.fi/en/publications/a2fd1d39-5d6d-44d1-bc90-463675bdbfae
https://cris.vtt.fi/en/publications/a2fd1d39-5d6d-44d1-bc90-463675bdbfae
Publikováno v:
Valo, M, Lappalainen, P, Lyytikäinen, T, Lydman, J & Paasila, M 2013, Advanced surveillance technique and embrittlement modelling (SURVIVE) . in SAFIR2014: The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014 : Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Technology, no. 80, pp. 313-323 . < https://publications.vtt.fi/pdf/technology/2013/T80.pdf#page=315 >
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::a5c52476bf1b56c9de2051c2beadae1d
https://cris.vtt.fi/en/publications/bcd90d63-b444-470e-8f09-2aa7b66fef80
https://cris.vtt.fi/en/publications/bcd90d63-b444-470e-8f09-2aa7b66fef80