Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Mykola Ivanchenko"'
Publikováno v:
Huotilainen, C, Ivanchenko, M, Efsing, P & Ehrnsten, U 2019, ' Electrochemical investigation of in-service thermal aging in two CF8M cast stainless steels ', Journal of Nuclear Materials, vol. 520, pp. 34-40 . https://doi.org/10.1016/j.jnucmat.2019.04.001
In-service thermal aging of CF8M cast austenitic stainless steel was investigated in materials removed from the steam generator inlet and crossover elbows of the Ringhals 2 pressurized water reactor nuclear power plant unit after approximately 92kh o
Publikováno v:
Anderson, K R, Karlsen, W, Ivanchenko, M, Carter, J J & Smith, R W 2019, ' Microstructural examination of zirconium alloys following in-pile creep testing in the HALDEN reactor ', Journal of Nuclear Materials, vol. 513, pp. 260-270 . https://doi.org/10.1016/j.jnucmat.2018.11.013
Post-irradiation examination (PIE) in the form of transmission electron microscopy (TEM) was used to characterize the microstructure of several specimens of Zircaloy-2 and Zircaloy-2 plus 1% Nb that had previously underwent in-pile creep testing in t
Autor:
Tatyana Syrenko, Mykola Ivanchenko
Publikováno v:
Bulletin of Kharkov National Automobile and Highway University. :73
A significant number of heat and power equipment, including welded connections of steam pipelines made of 15x1m1f and 12x1mf Steels, have now reached the design service life. Their practical experience is about 200,000 hours at an estimated temperatu
Autor:
Mykola Ivanchenko, Ulla Ehrnstén, Roman Mouginot, Young Suk Kim, Teemu Sarikka, Hannu Hänninen, Sung Soo Kim, Mikko Heikkilä
Publikováno v:
Mouginot, R, Sarikka, T, Heikkilä, M, Ivanchenko, M, Ehrnstén, U, Kim, Y S, Kimsung, S & Hänninen, H 2017, ' Thermal ageing and short-range ordering of Alloy 690 between 350 and 550 °C ', Journal of Nuclear Materials, vol. 485, pp. 56-66 . https://doi.org/10.1016/j.jnucmat.2016.12.031
Thermal ageing of Alloy 690 triggers an intergranular (IG) carbide precipitation and is known to promote an ordering reaction causing lattice contraction. It may affect the long-term primary water stress corrosion cracking (PWSCC) resistance of press
Autor:
Janne Heikinheimo, Caitlin Huotilainen (Hurley), Rami Pohja, Mykola Ivanchenko, Henri Loukusa
Publikováno v:
Heikinheimo, J, Huotilainen, C, Pohja, R, Ivanchenko, M & Loukusa, H 2019, Advanced cladding materials for accident tolerant fuels . in SYP2019 Proceedings . Finnish Nuclear Society, Nuclear Science and Technology Symposium, NST 2019, Helsinki, Finland, 20/10/19 . < https://ats-fns.fi/images/files/2019/syp2019/presentations/TSFM1_HLoukusa_AdvancedCladdingMaterialsForAccidentTolerantFuels_Tier1paper.pdf >
VTT Technical Research Centre of Finland-PURE
VTT Technical Research Centre of Finland-PURE
In terms of safety, nuclear fuel cladding is one of the main barriers in preventing the release of radioactive materials to the environment.The integrity of the fuel cladding is essential both in operation and in the long-term storage of spent nuclea
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::f2658f5c1e17b4ccd3a67441fc178fe5
https://cris.vtt.fi/en/publications/ff4317df-d873-4dd9-a1e2-da917fa8077e
https://cris.vtt.fi/en/publications/ff4317df-d873-4dd9-a1e2-da917fa8077e
Autor:
Roman Mouginot, Teemu Sarikka, Mikko Heikkilä, Mykola Ivanchenko, Unto Tapper, Ulla Ehrnstén, Hannu Hänninen
Publikováno v:
The Minerals, Metals & Materials Series ISBN: 9783030046385
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c26a1255ca54aaf26f93676e073756dc
https://doi.org/10.1007/978-3-030-04639-2_21
https://doi.org/10.1007/978-3-030-04639-2_21
Publikováno v:
Lagerbom, J, Lintunen, P, Ivanchenko, M, Metsäjoki, J, Oksa, M & Virta, J 2016, Economical Processing Route of ODS Material by Controlled Surface Oxidation of FE 9Cr Powder . in Proceedings of World PM2016 . European Powder Metallurgy Association (EPMA), World Powder Metallurgy Congress and Exhibition, WorldPM 2016, Hamburg, Germany, 9/10/16 .
Scopus-Elsevier
Scopus-Elsevier
Oxide dispersion strengthened steel can be manufactured without mechanical alloying by gas atomization of Cr-steel powder alloyed with high oxygen affinity element like yttrium, titanium and hafnium, surface oxidation of the powder particles, and HIP
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::7cfb77cdc480ac5c8a8ef6d7863c557e
https://cris.vtt.fi/en/publications/d166d980-9119-4e1a-bea1-3c01b8265512
https://cris.vtt.fi/en/publications/d166d980-9119-4e1a-bea1-3c01b8265512
Publikováno v:
Solid State Phenomena. 184:122-127
Two oxygen-free copper grades with purity of 99.99 % were studied by means of free decay inverted torsion pendulum at the temperature range of 90 – 300 K and frequencies of 0.5 – 2 Hz. One copper grade was oxygen free electrolytically refined cop
Publikováno v:
Solid State Phenomena. 184:227-232
Mechanical loss of pre-strained and hydrogen-charged specimens of 316L austenitic stainless steel has been measured by the free-decay method using an inverted torsion pendulum at frequencies around 1 Hz. It is found that in addition to known hydrogen
Publikováno v:
Karlsen, W, Ivanchenko, M, Ehrnstén, U, Yagodzinskyy, Y & Hänninen, H 2009, ' Microstructural manifestation of dynamic strain aging in AISI 316 stainless steel ', Journal of Nuclear Materials, vol. 395, no. 1-3, pp. 156-161 . https://doi.org/10.1016/j.jnucmat.2009.10.047
Dynamic strain aging (DSA) affects a material’s mechanical behaviour. In the current study, the deformation microstructures of AISI 316 stainless steel specimens were examined after tensile testing at several temperatures both in and out of the DSA