Konstantin Mikityuk
EPFL SB IPHYS LRS
PH D3 465 (Bâtiment PH)
Station 3
1015 Lausanne
+41 56 310 23 85
Office: PH D3 465
EPFL › SB › IPHYS › LRS
Site web: https://lrs.epfl.ch/
Formation
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1999 – 2002 PostGraduate School of Russian Research Сentre “Kurchatov Instituteâ€, Moscow, Russia
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1984 – 1992 Moscow Engineering Physics Institute, Russia
Expériences professionnelles
2023
Extension, validation, and optimization of Serpent/DYN3D/ATHLET code system for SFR applications
Lausanne, EPFL, 2023. DOI : 10.5075/epfl-thesis-9024.Simulation of flow and heat transfer in a differentially heated cubical cavity using coarse Large Eddy Simulation
International Journal Of Thermal Sciences. 2023-01-01. DOI : 10.1016/j.ijthermalsci.2022.107892.2022
On the Capability of Wall-Modeled Large Eddy Simulations to Predict Particle Dispersion in Complex Turbulent Flows
Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-10054.Advanced methodologies for modeling and assessment of SFR safety functions
Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-9289.CFD Simulation of Particle-Laden Flow in a 3D Differentially Heated Cavity Using Coarse Large Eddy Simulation
Flow, Turbulence and Combustion. 2022-08-16. DOI : 10.1007/s10494-022-00356-4.Modeling and assessment of high-temperature photo-electrochemical devices
Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-8169.Interface Tracking Investigation of the Sliding Bubbles Effects on Heat Transfer in the Laminar Regime
Nuclear Technology. 2022. DOI : 10.1080/00295450.2021.1971025.2021
Flow Simulation of Gas Cyclone Separator at High Reynolds Number Using theElliptic-Relaxation Hybrid LES/RANS (ER-HRL) Model
2021-06-18. 6th World Congress on Momentum, Heat and Mass Transfer (MHMT'21), Online (after cancellation of Lisbon Portugal event), June 17-19, 2021. DOI : 10.11159/icmfht21.lx.110.Particle subgrid scale modeling in hybrid RANS/LES of turbulent channel flow at low to moderate Reynolds number
Jounral of Powder Technology. 2021-11-27. DOI : 10.1016/j.powtec.2021.11.057.Improved methodology for analysis and design of Molten Salt Reactors
Lausanne, EPFL, 2021. DOI : 10.5075/epfl-thesis-8618.Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing-Part II: Methodology application
Annals Of Nuclear Energy. 2021-12-01. DOI : 10.1016/j.anucene.2021.108541.Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - Part I: Methodology demonstration
Annals Of Nuclear Energy. 2021-06-01. DOI : 10.1016/j.anucene.2021.108183.2019
A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design
Nuclear Engineering And Design. 2019-12-15. DOI : 10.1016/j.nucengdes.2019.110291.Preparation of high-conductivity, high-capacity phase change media capsules with enhanced thermos-chemical stability in thermal energy storage applications
Lausanne, EPFL, 2019. DOI : 10.5075/epfl-thesis-9715.2018
Creation Of An Openfoam Fuel Performance Class Based On Fred And Integration Into The Gen-Foam Multi-Physics Code
2018-01-01. 26th International Conference on Nuclear Engineering (ICONE-26), London, ENGLAND, Jul 22-26, 2018. p. V003T02A027. DOI : 10.1115/ICONE26-81574.A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors
2018-01-01. 26th International Conference on Nuclear Engineering (ICONE-26), London, ENGLAND, Jul 22-26, 2018. p. V004T15A018. DOI : 10.1115/ICONE26-82260.Analytical solutions to a coupled fluid dynamics and neutron transport problem with application to GeN-Foam verification
Annals of Nuclear Energy. 2018-11-01. DOI : 10.1016/j.anucene.2018.07.036.2017
Modelling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light Water Reactor
Lausanne, EPFL, 2017. DOI : 10.5075/epfl-thesis-8018.2013
A wrapper tube for a fuel subassembly of a nuclear reactor core and method for protecting fuel against overheating in case of coolant boiling
WO2013098079 ; EP2610875 . 2013.Coupled 3-D Neutronics/Thermal-Hydraulics Optimization Study For Improving The Response Of A 3600 Mw(Thermal) Sfr Core To An Unprotected Loss-Of-Flow Accident
Nuclear Technology. 2013. DOI : 10.13182/NT13-A19436.2012
Analysis of selected Phenix EOL tests with the FAST code system - Part II: Unprotected phase of the Natural Convection Test
Annals Of Nuclear Energy. 2012. DOI : 10.1016/j.anucene.2012.05.035.Analysis of selected Phenix EOL tests with the FAST code system - Part I: Control-rod-shift experiments
Annals Of Nuclear Energy. 2012. DOI : 10.1016/j.anucene.2012.05.036.Analysis of the BN-600 fast-spectrum core mock-up at BFS-2 zero-power facility using MCNPX
Annals Of Nuclear Energy. 2012. DOI : 10.1016/j.anucene.2012.01.011.A standalone decay heat removal device for the Gas-cooled Fast Reactor for intermediate to atmospheric pressure conditions
Nuclear Engineering And Design. 2012. DOI : 10.1016/j.nucengdes.2011.10.011.2011
The generation IV gas-cooled fast reactor
2011. ICAPP 2011 - Performance and Flexibility: The Power of Innovation, Nice, France, May 2-5, 2011. p. 238-244.Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle
Annals Of Nuclear Energy. 2011. DOI : 10.1016/j.anucene.2011.02.018.Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow
Nuclear Engineering And Design. 2011. DOI : 10.1016/j.nucengdes.2011.07.009.2010
Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions
2010. 4th International Topical Meeting on High Temperature Reactor Technology, Washington, DC, Sep 28-Oct 01, 2008. p. 3115-3125. DOI : 10.1016/j.nucengdes.2010.05.030.TRACE qualification via analysis of the EIR gas-loop experiments with smooth rods
Annals Of Nuclear Energy. 2010. DOI : 10.1016/j.anucene.2010.01.020.FAST code system: Review of recent developments and near-future plans
Journal of Engineering for Gas Turbines and Power. 2010. DOI : 10.1115/1.4000336.2009
EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors
Annals of Nuclear Energy. 2009. DOI : 10.1016/j.anucene.2009.01.008.Heat transfer to liquid metal: Review of data and correlations for tube bundles
Nuclear Engineering and Design. 2009. DOI : 10.1016/j.nucengdes.2008.12.014.Development and benchmarking of a mechanical model for GFR plate-type fuel
Annals of Nuclear Energy. 2009. DOI : 10.1016/j.anucene.2009.01.015.TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions
Nuclear Engineering and Design. 2009. DOI : 10.1016/j.nucengdes.2009.07.015.2008
Verification of the TRACE Code against the MEGAPIE Transient Data
Annals of Nuclear Energy. 2008. DOI : 10.1016/j.anucene.2007.12.006.Analysis of radioactivity releases in the MEGAPIE reference accident
Nuclear Engineering and Design. 2008. DOI : 10.1016/j.nucengdes.2007.12.004.Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor
Annals of Nuclear Energy. 2008. DOI : 10.1016/j.anucene.2008.09.008.2007
Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel
Annals of Nuclear Energy. 2007. DOI : 10.1016/j.anucene.2007.03.009.Comparative transient analysis of critical and subcritical 80-MW Pb-Bi eutectic-cooled reactor systems
Nuclear Technology. 2007. DOI : 10.13182/NT07-A3799.2006
Calculations of Reactivity-Initiated Transients in Gas-Cooled Fast Reactors Using the Code System FAST
Annals of Nuclear Energy. 2006. DOI : 10.1016/j.anucene.2006.01.002.Comparison of the transient behaviour of LBE-and gas-cooled experimental accelerator-driven systems
Nuclear Engineering and Design. 2006. DOI : 10.1016/j.nucengdes.2006.03.012.2005
FAST: An advanced code system for fast reactor transient analysis
Annals of Nuclear Energy. 2005. DOI : 10.1016/j.anucene.2005.06.002.Development of a drift-flux model for heavy liquid metal/gas flow
Journal of Nuclear Science and Technology. 2005. DOI : 10.3327/jnst.42.600.Enseignement et PhD
Doctorant·es actuel·les
Diego Mondaray Muñoz, Alessio Rossi
A dirigé les thèses EPFL de
Rodrigo Gonzalez Gonzaga De Oliveira, Janos Bodi, Mohamed Aly Hashem Mohamed Sayed, Vincenzo Anthony Di Nora