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Volodymyr M. Revka

Observed names: Revka, V., V. M. Revka, V. Revka, V.M. Revka, Volodymyr Revka, Ревка , В. М., Ревка, В. М.
ORCID: 0000-0002-8409-263X
Observed ORCID: 0000-0002-8409-263X
OpenAlex ID: A5058340717
Chemical Composition Effect on Radiation Embrittlement and Hardening of WWER-1000 RPV Steels
2023 · Maksym Zarazovskii, Volodymyr Revka, et al. · 3
Формування підходів до реалізації програми зразків-свідків під час впровадження паливних збірок ТВЗ-WR на реакторах ВВЕР-1000
2024 · V. Bukanov, O. Grytsenko, et al. · Nuclear and Radiation Safety · 2
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A Physically-Based Criterion for Determining the Critical Brittleness Temperature from Charpy Impact PRV Tests for Reactor Steels and Their Welds
2024 · S. Kotrechko, V. Revka, et al. · METALLOFIZIKA I NOVEISHIE TEKHNOLOGII · 2
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The use of master curve method for statistical re-evaluation of surveillance test data for WWER-1000 reactor pressure vessels
2010 · V. M. Revka, E. U. Grynik, et al. · Strength of Materials · 2
Radiation hardening and embrittlement of the base and weld metal of VVER-1000 reactor pressure vessels
2025 · S. Kotrechko, O. Zatsarna, et al. · International Journal of Pressure Vessels and Piping · 1
Comparison of Маster curve with normative method of estimating WWER-1000 reactor pressure vessel metal fracture toughness
2024 · V.M. Revka, L.I. Chyrko · Nuclear Physics and Atomic Energy · 1
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Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs
2020 · Maksym Zarazovskii, Volodymyr Revka, et al. · ASME Pressure Vessels and Piping Conference (PVP) · 1
Radiation embrittlement of reactor pressure vessel materials of Rivne NPP unit 1 due to re-irradiation after recovery annealing
2019 · M.G. Holiak, G.P. Grynchenko, et al. · Nuclear Physics and Atomic Energy · 1
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A Data Scatter for a Shift of the Ductile to Brittle Transition Temperature for WWER-1000 Reactor Pressure Vessel Materials
2018 · V. Revka · Nuclear and Radiation Safety · 1
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Issue of Application for the Pre-Cracked Charpy Specimens to Estimate WWER-1000 RPV Metal Embrittlement
2016 · Volodymyr M. Revka, Liudmyla I. Chyrko · ASME Pressure Vessels and Piping Conference (PVP) · 1
Embrittlement Behavior of the RPV Metal of Power Unit No. 2 at the Zaporozhye NPP
2013 · V. M. Revka, O. V. Trygubenko, et al. · Strength of Materials · 1
Mechanical stability paradigm for prediction of rpv service life
2012 · Kotrechko, S., Meshkov, Yu., et al. · arXiv (Cornell University) · 1
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A new method for determining the threshold level of impact energy for reactor pressure vessel metal
2025 · S. Kotrechko, K. Soroka, et al. · International Journal of Pressure Vessels and Piping
Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of Wwer-1000 Rpvs
2021 · Maksym Zarazovskii, Volodymyr Revka, et al.
Weld metal irradiation embrittlement analysis in the range of over-design neutron fluences
2020 · L.I. Chyrko, V.M. Revka, et al. · Nuclear Physics and Atomic Energy
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To the issue of accuracy of determination of irradiation embrittlement coefficient
2020 · L.I. Chyrko, V.M. Revka, et al. · Nuclear Physics and Atomic Energy
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Engineering Version of Local Approach to Fracture and its Application for RPV Lifetime Prediction
2019 · Sergiy Kotrechko, Galyna Zimina, et al. · Key engineering materials
Новий підхід до оцінки критичної температури крихкості металу корпусу реактора ВВЕР-1000
2017 · V. Revka, Г. П. Гринченко, et al. · ELARTU (Ternopil National Technical University)
Application of Master Curve Approach to Surveillance Test Data for WWER-1000 Reactor Pressure Vessels
2017 · Volodymyr M. Revka, Liudmyla I. Chyrko · ASME Pressure Vessels and Piping Conference (PVP)
Different approaches to estimation of reactor pressure vessel material embrittlement
2013 · V.M. Revka, L.I. Chyrko, et al. · Nuclear Physics and Atomic Energy
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Використання результатів випробувань зразків-свідків для оцінки критичної температур крихкості корпусних матеріалів реактора ВВЕР-1000
2005 · Гринік, Е. У., Ревка , В. М., et al. · Nuclear and Radiation Safety
Assessment of WWER-type reactor vessels radiation lifetime of Ukrainian NPPS
2005 · E.U. Grynik, L.I. Chyrko, et al. · Nuclear Physics and Atomic Energy
Reactor pressure vessel operation life-time determination by surveillance samples testing
2001 · E. Grynik, L. Chyrko, et al. · Nuclear Physics and Atomic Energy
Works count: 26
Citation count: 17
H-index: 2
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