Zobrazeno 1 - 10 of 19 pro vyhledávání: '"Ivanchenko, Mykola"'
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Akademický článek
Microstructural manifestation of dynamic strain aging in AISI 316 stainless steel
Autor: Karlsen, Wade, Ivanchenko, Mykola, Ehrnstén, Ulla, Yagodzinskyy, Yuriy, Hänninen, Hannu
Publikováno v: In Journal of Nuclear Materials 2009 395(1):156-161
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3
Development of short-range order and intergranular carbide precipitation in Alloy 690 TT upon thermal ageing
Autor: Mouginot, Roman, Sarikka, Teemu, Heikkilä, Mikko, Ivanchenko, Mykola, Tapper, Unto, Ehrnstén, Ulla, Hänninen, Hannu
Publikováno v: Mouginot, R, Sarikka, T, Heikkilä, M, Ivanchenko, M, Tapper, U, Ehrnstén, U & Hänninen, H 2018, Development of short-range order and intergranular carbide precipitation in Alloy 690 TT upon thermal ageing . in D Paraventi, M Wright & J H Jackson (eds), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors . Springer, Minerals, Metals and Materials Series, vol. Part F9, pp. 321-334, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 2017, Portland, United States, 13/08/17 . https://doi.org/10.1007/978-3-319-67244-1_21
Thermal ageing promotes intergranular carbide precipitation and atomic ordering reaction in most commercial nickel-base alloys, and it affects the long-term primary water stress corrosion cracking (PWSCC) resistance of pressurized water reactor compo
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::17d5c5e984f71da9a220f40c4de4e173
https://cris.vtt.fi/en/publications/268ac43d-5765-412b-9fe5-27c214435e20
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4
Microstructural investigations of the 300-series austenitic stainless steels irradiated to different fluences after in-pile mechanical test
Autor: Ivanchenko, Mykola, Ehrnstén, Ulla, Karlsen, Torill
Publikováno v: Ivanchenko, M, Ehrnstén, U & Karlsen, T 2018, Microstructural investigations of the 300-series austenitic stainless steels irradiated to different fluences after in-pile mechanical test . in Proceedings of Fontevraud 9 : Contribution of Materials Investigation and Operating Experience to Light Water NPPs Safety, Performance and Reliability . French Nuclear Energy Society (SFEN), Fontevraud 9 : Contribution of Materials Investigation and Operating Experience to Light Water NPPs Safety, Performance and Reliability, Avignon, France, 17/09/18 .
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::bd40f39603c703ca13bce53f93372747
https://cris.vtt.fi/en/publications/f3a68422-62ec-4fe7-9667-313192ced6b0
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5
Akademický článek
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6
Thermal ageing and EAC research for plant life management (THELMA)
Autor: Ehrnstén, Ulla, Ahonen, Matias, Autio, Juha-Matti, Ivanchenko, Mykola, Hurley, Caitlin, Toivonen, Aki, Mouginot, Roman, Ilola, Risto, Hänninen, Hannu
Publikováno v: Ehrnstén, U, Ahonen, M, Autio, J-M, Ivanchenko, M, Hurley, C, Toivonen, A, Mouginot, R, Ilola, R & Hänninen, H 2017, Thermal ageing and EAC research for plant life management (THELMA) . in J Hämäläinen & V Suolanen (eds), SAFIR2018-The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018 : Interim Report . VTT Technical Research Centre of Finland, VTT Technology, vol. 294, pp. 319-330 .
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::c7bc72fb8125b21bd109b121c9745a15
https://cris.vtt.fi/en/publications/665dc780-1a69-43fc-8b60-e09fdae5d340
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7
Microstructural TEM Examination of 2 dpa Irradiated 304L Stainless Steel Extracted from a Tensile Creep Specimen from IFA-669
Autor: Ivanchenko, Mykola
Publikováno v: Ivanchenko, M 2016, ' Microstructural TEM Examination of 2 dpa Irradiated 304L Stainless Steel Extracted from a Tensile Creep Specimen from IFA-669 ', Paper presented at 39th Enlarged Halden Programme Group Meeting, EHPG 2016, Fornebu, Norway, 8/05/16-13/05/16 .
Microstructural examinations were performed in order to test the hypothesis on the mechanism of initial shrinkage observed in the solution annealed 304L stainless steel tested in irradiation creep experiment IFA 669. Analytical transmission electron
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::1ea644b56c326d247b9026880b99570b
https://cris.vtt.fi/en/publications/7ed05586-aee3-47e5-929d-85610bc1c9ee
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8
Thermal Aging Induced Phase Transformations in Nuclear Grade Typr 316L Stainless Steel Weld Metals
Autor: Ivanchenko, Mykola, Ehrnstén, Ulla, Forsström, Antti, Hänninen, Hannu, Ballinger, Ronald G.
Publikováno v: Ivanchenko, M, Ehrnstén, U, Forsström, A, Hänninen, H & Ballinger, R G 2016, ' Thermal Aging Induced Phase Transformations in Nuclear Grade Typr 316L Stainless Steel Weld Metals ', Paper presented at 14th International Conference on Material Issues in Desing, Manufacturing and Operation of Nuclear Power Plants Equipment, Mainstream-2016, St. Petersburg, Russian Federation, 6/06/16-10/06/16 .
Microstructural investigations of thermally aged nuclear grade type 316L stainless steel welds were performed by electron microscopy methods. The microstructures of the thermally aged welds were compared to non-aged condition. Characterization of the
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::cbefa4d718784ae3fec0cf42613ca554
https://cris.vtt.fi/en/publications/732e7292-b715-4518-aa26-b0070fa0e2ca
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9
TEM examination of the effect of post-irradiation annealing on 7.7 dpa AISI 304 stainless steel
Autor: Karlsen, Wade, Ivanchenko, Mykola, Pakarinen, Janne, Karlsen, Torill
Publikováno v: Karlsen, W, Ivanchenko, M, Pakarinen, J & Karlsen, T 2014, TEM examination of the effect of post-irradiation annealing on 7.7 dpa AISI 304 stainless steel . in Fontevraud 8 : Conference on Contribution of Materials Investigations and Operating Experience to LWRs' Safety, Performance and Reliability . French Nuclear Energy Society (SFEN), Fontevraud 8, Avignon, France, 15/09/14 .
Analytical transmission electron microscopy (ATEM) was used to examine the effect of post-irradiation annealing (PIA) on radiation-induced segregation (RIS) at the grain boundaries of 7.7 dpa AISI 304 stainless steel. The grain boundary profiles and
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::c69278e2357edc68bc3da5105b715f9f
https://cris.vtt.fi/en/publications/28f5ed76-ee3b-4819-b8d4-f4b10f57c44f
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10
Influence of Material, Environment and Strain Rate on Environmentally Assisted Cracking of Austenitic Nuclear Materials (DEFSPEED):DEFSPEED summary report
Autor: Ehrnstén, Ulla, Karlsen, Wade, Pakarinen, Janne, Ahonen, Matias, Kuivalainen, Pasi, Ivanchenko, Mykola, Saukkonen, Tapio, Hänninen, Hannu
Publikováno v: Ehrnstén, U, Karlsen, W, Pakarinen, J, Ahonen, M, Kuivalainen, P, Ivanchenko, M, Saukkonen, T & Hänninen, H 2011, Influence of Material, Environment and Strain Rate on Environmentally Assisted Cracking of Austenitic Nuclear Materials (DEFSPEED) : DEFSPEED summary report . in SAFIR2010: The Finnish Research Programme on Safety 2007-2010 : Final Report . VTT Technical Research Centre of Finland, VTT Tiedotteita-Research Notes, no. 2571, pp. 440-452 . < https://publications.vtt.fi/pdf/tiedotteet/2011/T2571.pdf >
The DEFSPEED project (Influence of material, environment and strain rate on environmentally assisted cracking on austenitic nuclear materials) focussed on increasing the understanding of environmentally assisted cracking (EAC) and irradiation assiste
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::f54b1fab1c60220c11079fde2607ee01
https://cris.vtt.fi/en/publications/ced191be-b744-448d-a17b-9b0511ad2f0d
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