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Yaroslav Dubyk
Yaroslav Dubyk
IPP-Centre LLC
在 ipp-centre.com.ua 的电子邮件经过验证
标题
引用次数
引用次数
年份
Application of the transfer matrix method to the analysis of hydro-mechanical vibration of NPP piping
I Orynyak, S Radchenko, I Dubyk
Pressure Vessels and Piping Conference 55683, V004T04A049, 2013
132013
Approximate formulas for cylindrical shell free vibration based on Vlasov’s and enhanced Vlasov’s semi-momentless theory
I Orynyak, Y Dubyk
Pressure Vessels and Piping Conference 51715, V008T08A050, 2018
122018
An application of the transfer matrix approach for a dynamic analysis of complex spatial pipelines
A Batura, A Novikov, A Pashchenko, Y Dubyk
Nuclear Engineering and Design 349, 174-182, 2019
102019
Application of the method of initial parameters to analysis of coupled hydromechanical vibrations in piping systems. Part 2. Natural frequencies and modes of coupled …
IV Orynyak, AS Batura, YR Dubik
Strength of Materials 44, 8-19, 2012
102012
Dynamic assessment of the core barrel during loss of coolant accident
Y Dubyk, V Filonov, O Ishchenko, I Orynyak, Y Filonova
Pressure Vessels and Piping Conference 51654, V004T04A035, 2018
92018
Analysis of water hammer due to sudden rupture of reactor coolant system
I Dubyk, I Orynyak
Pressure Vessels and Piping Conference 50404, V004T04A021, 2016
92016
The application of the combined method of weight functions for the determination of a through-wall crack opening area in a shell
IV Orynyak, ES Yakovleva, YR Dubik
Strength of Materials 44, 600-616, 2012
92012
An exact series solution for free vibration of cylindrical shell with arbitrary boundary conditions
Y Dubyk, I Orynyak, O Ishchenko
Вісник Тернопільського національного технічного університету 89 (1), 79-88, 2018
72018
A new simple method for shell vibration analysis with initial stress accounting
D Yaroslav, I Oleksii, K Mykola
Procedia Structural Integrity 26, 422-429, 2020
62020
Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles
Y Dubyk, V Filonov, Y Filonova, O Kovalenko
Journal of Nuclear Engineering and Radiation Science 8 (3), 031105, 2022
52022
Transfer matrix method for analysis of flow thermohydraulic characteristics with extremely nonlinear behavior of thermophysical properties using channel approach
V Filonov, Y Filonova, Y Dubyk, E Pis' mennyi
International Journal of Heat and Mass Transfer 187, 122531, 2022
52022
Impact of the Outer Surface Air Cooling and WPS Approaches on the Brittle Fracture Margin of WWER RPV
M Zarazovskii, Y Dubyk, V Filonov, V Antonchenko, O Ishchenko
Pressure Vessels and Piping Conference 83860, V006T06A016, 2020
52020
Swelling of the WWER-1000 Reactor Core Baffle
D Yaroslav, F Vladislav, F Yuliia
IASMiRT, 2019
52019
Application of Probabilistic Leak-Before-Break for WWER-1000 Unit
Y Dubyk
Procedia Structural Integrity 22, 275-282, 2019
52019
Assessment of dents for gas pipelines
Y Dubyk, I Seliverstova
Procedia Structural Integrity 18, 622-629, 2019
52019
Analysis of fluid-induced vibrations of long branched pipelines
IV Orynyak, YR Dubyk, AS Batura
Strength of Materials 47, 314-331, 2015
52015
Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment
Y Filonova, Y Dubyk, V Filonov, V Kondratjuk
Journal of Nuclear Engineering and Radiation Science 7 (1), 011404, 2021
42021
Calculation of VVER-1000 core baffle temperature distribution for it's swelling assessment
V Filonov, Y Filonova, Y Dubyk, A Bohdan
Proceedings of Odessa Polytechnic University 1, 35-45, 2020
4*2020
Reactor baffle cooling CFD framework for swelling assessment
Y Filonova, V Filonov, Y Dubyk
International Conference on Nuclear Engineering 51531, V009T16A079, 2018
42018
Fluid-structure interaction in free vibration analysis of pipelines
IR Dubyk, IV Orynyak
Вісник Тернопільського національного технічного університету 81 (1), 49-58, 2016
42016
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