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Jan Škarohlíd

Observed names: J. Škarohlíd, Jan Skarohlid, Škarohlíd, J., Škarohlíd, Jan
ORCID: 0000-0002-2854-0047
Observed ORCID: 0000-0002-2854-0047
OpenAlex ID: A5058010686
Nanosized polycrystalline diamond cladding for surface protection of zirconium nuclear fuel tubes
2014 · I. Kratochvílová, R. Škoda, et al. · Journal of Materials Processing Technology · 39
Thin polycrystalline diamond films protecting zirconium alloys surfaces: From technology to layer analysis and application in nuclear facilities
2015 · P. Ashcheulov, R. Škoda, et al. · Applied Surface Science · 38
Zr alloy protection against high-temperature oxidation: Coating by a double-layered structure with active and passive functional properties
2019 · Irena Kratochvílová, Petr Ashcheulov, et al. · Corrosion Science · 27
Nanocrystalline diamond protects Zr cladding surface against oxygen and hydrogen uptake: Nuclear fuel durability enhancement
2017 · Jan Škarohlíd, Petr Ashcheulov, et al. · Scientific Reports · 21
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Influence of local grid refinement on prediction of impinging jet heat transfer using Scale-Resolving-Simulation methods
2022 · Tomáš Kořínek, Karel Fraňa, et al. · Case Studies in Thermal Engineering · 8
Layer Protecting the Surface of Zirconium Used in Nuclear Reactors
2016 · Petr Ashcheulov, Radek Skoda, et al. · Recent Patents on Nanotechnology · 8
Current Progress in R&D of Fluoride Volatility Method
2012 · Jan Uhlíř, Martin Mareček, et al. · Procedia Chemistry · 8
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TEPLATOR: Nuclear district heating solution
2020 · Radek Škoda, Anna Fořtová, et al. · Digital Library (University of West Bohemia) · 6
Numerical and experimental investigation of melting and solidification of molten salt in freeze valve
2025 · Mahmut Cüneyt Kahraman, Tomas Korinek, et al. · Applied Thermal Engineering · 3
Molten Salt Freeze Valve Operation: Experimental Study
2025 · T. Kořínek, M. C. Kahraman, et al. · Topical Problems of Fluid Mechanics · 1
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Polycrystalline Diamond Coating Protects Zr Cladding Surface Against Corrosion in Water‐Cooled Nuclear Reactors: Nuclear Fuel Durability Enhancement
2018 · Irena Kratochvílová, Radek Škoda, et al. · Wiley eBooks · 1
Polycrystalline Diamond Films as Protection of Zircaloy Fuel Cladding
2014 · Jan Škarohlíd, Radek Škoda · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
Current status of fluoride volatility method development
2013 · Jan Uhlíř, Martin Mareček, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
Delayed Detached Eddy Simulation of Thermal Mixing in T-Junction
2024 · T. Kořínek, J. Škarohlíd, et al. · Topical Problems of Fluid Mechanics
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Advanced Coatings of Nuclear Fuel Cladding
2018 · Jan Škarohlíd · Czech Technical University Digital Library (Czech Technical University in Prague)
High Temperature Oxidation of Polycrystalline Diamond Coated Zirconium Alloy
2016 · Jan Škarohlíd, Radek Škoda, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Antikorozní ochrana povrchu zirkoniových slitin kompozitními polykrystalickými diamantovými vrstvami
2016 · Kratochvílová, I. (Irena), Ashcheulov, P. (Petr), et al. · ASEP
Vrstva, chránící povrch zirkoniových slitin užívaných v jaderných reaktorech
2015 · Škoda, R., Škarohlíd, J., et al. · ASEP
Protection of Zircaloy nuclear fuel rods using nanocrystalline diamond coatings
2015 · Ashcheulov, P. (Petr), Taylor, A. (Andrew), et al. · ASEP
Vrstva chránící povrch zirkoniových slitin užívaných v jaderných reaktorech
2014 · Škoda, P., Škarohlíd, J., et al. · ASEP
Works count: 21
Citation count: 162
H-index: 7
I10-index: 4
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