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Ladislav Vyskocil

Observed names: L. Vyskocil, L. Vyskočil, Vyskočil, Ladislav
ORCID: 0000-0003-2963-6304
Observed ORCID: 0000-0003-2963-6304
OpenAlex ID: A5018145580
Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor—Validation of CFD codes
2007 · U. Rohde, T. Höhne, et al. · Nuclear Engineering and Design · 100
CFD simulation of air–steam flow with condensation
2014 · Ladislav Vyskocil, Josef Schmid, et al. · Nuclear Engineering and Design · 98
Lesson learned from the SARNET wall condensation benchmarks
2014 · W. Ambrosini, N. Forgione, et al. · Annals of Nuclear Energy · 34
Comparison and Analysis of the Condensation Benchmark Results
2008 · Walter Ambrosini, Matteo Bucci, et al. · CINECA IRIS Institutial research information system (University of Pisa) · 34
Review of Available Data for Validation of Nuresim Two‐Phase CFD Software Applied to CHF Investigations
2008 · D. Bestion, H. Anglart, et al. · Science and Technology of Nuclear Installations · 29
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Benchmark DEBORA: Assessment of MCFD compared to high-pressure boiling pipe flow measurements
2024 · G. Bois, P. Fillion, et al. · International Journal of Multiphase Flow · 26
Status of computational fluid dynamics for in-vessel retention: Challenges and achievements
2019 · A. Shams, D. Dovizio, et al. · Annals of Nuclear Energy · 21
Coupling CFD code with system code and neutron kinetic code
2014 · Ladislav Vyskocil, Jiri Macek · Nuclear Engineering and Design · 16
Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
2017 · I. Spasov, S. Mitkov, et al. · Nuclear Engineering and Design · 15
CFD simulation of critical heat flux in a tube
2012 · L. Vyskočil, Jiří Macek · 14
Multi-Scale Thermalhydraulic Analyses Performed in NURESIM and NURISP Projects
2012 · D. Bestion, D. Lucas, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 13
Gas entrainment by one single French PWR spray, SARNET-2 spray benchmark
2014 · J. Malet, S. Mimouni, et al. · Nuclear Engineering and Design · 12
Computational Fluid Dynamics Modeling of Boiling Bubbly Flow for Departure From Nucleate Boiling Investigations
2011 · Bostjan Koncar, C. Morel, et al. · Multiphase Science and Technology · 11
In-Vessel Melt Retention (IVMR) Analysis of a VVER-1000 NPP
2016 · Marco Sangiorgi, Aleksander Grah, et al. · Joint Research Centre (European Commission) · 8
Thermal Hydraulic Analyses for PTS Evaluation: Comparison of Temperature Fields at RPV Predicted by System TH Code and CFD Code
2018 · Pavel Kral, Ladislav Vyskocil · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 4
Thermal Hydraulic Experiments and Code Validation for LWR SMRs Within the European McSAFER Project: Overview of Activities and Current Status
2023 · H. Suikkanen, J. Telkkä, et al. · International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH) · 3
Simulation d'expériences à flux calorifique critique a l'aide du programme NEPTUNE_CFD
2009 · Ladislav Vyskocil, Jiri Macek · La Houille Blanche · 3
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Analysis of Pressurized Thermal Shocks for Inlet Nozzle of VVER Reactor Pressure Vessel
2015 · Vladislav Pištora, Miroslav Pošta, et al. · NCSU Libraries Repository (North Carolina State University Libraries) · 2
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Natural convection in a shallow pool heated from below and implications for the thermal focusing effect at the lateral wall
2024 · N. Seiler, M. Johnson, et al. · Nuclear Engineering and Design · 1
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State of the Art for Thermal-Hydraulic Analysis of Pressurised Thermal Shock Scenarios
2023 · Ivor Clifford, Pavel Kral, et al. · International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH) · 1
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Cfd Simulation Benchmark on Thermal-hydraulic Behaviour of Light Metal Layer
2023 · N. Seiler, B. Bian, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
Simulation of subcooled boiling in multiphase CFD code CFX / Simulation des unterkühlten Siedens im Mehrphasen-CFDCode CFX
2020 · L. Vyskočil, V. Železny, et al. · Kerntechnik · 1
The European project FLOMIX-R: Fluid mixing and flow distribution inthe reactor circuit - Final summary report
2010 · B. Hemström, P. Mühlbauer, et al. · Qucosa (Saxon State and University Library Dresden) · 1
CFD Simulation of Slug Mixing in VVER-1000 Reactor
2006 · Ladislav Vyskocil · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
Works count: 28
Citation count: 449
H-index: 12
I10-index: 13
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