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Vladimir Kriventsev

Observed names: Kriventsev V., Kriventsev, V., Kriventsev, Vladimir, V KRIVENTSEV, V. I. Kriventsev, V. KRIVENTSEV, V. Kriventsev, VLADIMIR KRIVENTSEV, Vladimir KRIVENTSEV
OpenAlex ID: A5023711573
Simulation of central sloshing experiments with smoothed particle hydrodynamics (SPH) method
2011 · Alexander Vorobyev, Vladimir Kriventsev, et al. · Nuclear Engineering and Design · 26
Application of safety analysis code SIMMER-IV to blockage accidents in FASTEF subcritical core
2013 · V. Kriventsev, A. Rineiski, et al. · Annals of Nuclear Energy · 21
Prevention and mitigation of severe accident developments and recriticalities in advanced fast reactor systems
2011 · Werner Maschek, Michael Flad, et al. · Progress in Nuclear Energy · 19
Numerical Prediction of Secondary Flows in Complex Areas Using Concept of Local Turbulent Reynolds Number
2003 · Vladimir KRIVENTSEV, Hiroyuki OHSHIMA, et al. · Journal of Nuclear Science and Technology · 10
Analysis of Central Sloshing Experiment Using Smoothed Particle Hydrodynamics (SPH) Method
2010 · Alexander Vorobyev, Vladimir Kriventsev, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 5
Vapor film collapse triggered by external pressure pulse and the fragmentation of melt droplet in FCIs
2008 · Q LIN, L TONG, et al. · Nuclear Science and Techniques · 5
Probabilistic Evaluation of the Post Disassembly Energetics of a Hypothetical Core Disruptive Accident in a Sodium-Cooled SMR by using a Phenomenological Relationship Diagram
2017 · Fabrizio Gabrielli, Michael Flad, et al. · Energy Procedia · 4
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A rule of minimal energy dissipation in modeling of channel flow turbulence
2016 · Vladimir Kriventsev · Numerical Heat Transfer Part B Fundamentals · 4
Neutronic Analysis of Start-Up Tests at China Experimental Fast Reactor
2022 · Jiwon Choe, Chirayu Batra, et al. · Energies · 3
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Bell–Plesset instability analysis for an inward centralized sloshing
2015 · R. Li, W. Maschek, et al. · Nuclear Engineering and Design · 3
Iaea’s Coordinated Research Projects on Thermal Hydraulics of Fast Reactors
2023 · ikoleta Morelová, Vladimir Kriventsev, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 2
IAEA NAPRO coordinated research project: physical properties of sodium. Overview of the reference database and preliminary analysis results
2017 · Stefano Passerini, Craig Gerardi, et al. · 2
Numerical Method for Simulation of Fluid Flow and Heat Transfer in Geometrically Disturbed Rod Bundles
2000 · Vladimir KRIVENTSEV, Hisashi NINOKATA · Journal of Nuclear Science and Technology · 2
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Program complex for hydraulic calculation of pressure losses on a personal computer
1991 · I. P. Smogalev, V. V. Anisimov, et al. · Atomic Energy · 2
Comprehensive Compilations of Computation Results and Validations for Neutronics Start-up Tests at China Experimental Fast Reactor
2022 · Jiwon Choe, Chirayu Batra, et al. · International Conference on Physics of Reactors (PHYSOR) · 1
Benchmark analyses of EBR-II shutdown heat removal tests
2018 · L.L. Briggs, Vladimir Kriventsev, et al. · 1
Application of a probabilistic relationship diagram for PDE mechanical energy release evaluation after HCDA in a Sodium-Cooled SMR
2016 · F. Gabrielli, Michael Flad, et al. · 1
Numerical Prediction of Secondary Flows in Complex Areas Using Concept of Local Turbulent Reynolds Number
2003 · Vladimir KRIVENTSEV, Hiroyuki OHSHIMA, et al. · Journal of Nuclear Science and Technology · 1
Multi-scale Viscosity (msv) Model of Turbulence
2002 · VLADIMIR KRIVENTSEV, AKIRA YAMAGUCHI, et al. · 1
IAEA Activities on Fast Reactors Technology
2026 · V. Kriventsev, N. Virgili, et al. · Zenodo (CERN European Organization for Nuclear Research)
IAEA Initiative on Open-source Tools for Nuclear Reactor Analysis
2025 · Nicole Virgili, Vladimir Kriventsev · Transactions of the American Nuclear Society
Coordinated Research Projects and Related IAEA Activities on Fast Reactor Technology
2025 · Nicole Virgili, Vladimir Kriventsev · Transactions of the American Nuclear Society
IAEA's Coordinated Research Projects and Activities on Thermal Hydraulics of Fast Reactors
2023 · Nikoleta Morelova, Vladimir Kriventsev, et al.
Iaea Initiative on Open-source Nuclear Codes for Reactor Analysis
2023 · Nikoleta Morelová, Vladimir Kriventsev, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Monte Carlo Simulation of Neutronics Start-up Tests at China Experimental Fast Reactor (cefr)
2021 · Jiwon Choe, Chirayu Batra, et al. · EPJ Web of Conferences
Works count: 49
Citation count: 115
H-index: 5
I10-index: 4
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