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
Website: https://lrs.epfl.ch/
Expertise
Generation-IV fast reactors, advanced modeling, coupled neutronics and thermal hydraulics, sodium boiling
Paul Scherrer Institut
Fast Reactors Group Leader
Laboratory for Reactor Physics and Systems Behaviour
Nuclear Energy and Safety Department
OHSA/D11
5232 Villigen PSI
Switzerland
E-mail: konstantin.mikityuk@psi.ch
Tel: +41 56 310 23 85
Since 1992 I have been involved in research of safety-related aspects of various nuclear reactors with fast neutron spectrum: first at Russian Kurchatov Institute and then at Swiss Paul Scherrer Institute. My current interests are safety analysis of sodium-cooled fast reactor, in particular neutronics and thermal-hydraulic aspects of sodium boiling.
Memberships
- Representative of Switzerland in Generation-IV International Forum (GIF)
- Co-chair of GIF Education and Training Task Force
- Representative of Switzerland in International Atomic Energy Agency Technical Working Group on Fast Reactors (IAEA TWG-FR)
Education
PhD in Nuclear Power Facilities
| Development and application of a complex transient code for fast reactors with lead-based coolant1999 – 2002 PostGraduate School of Russian Research Сentre “Kurchatov Instituteâ€, Moscow, Russia
MS in Nuclear Engineering
| Thesis on development and testing of advanced fuel thermal model1984 – 1992 Moscow Engineering Physics Institute, Russia
Professionals experiences
Advanced Nuclear Systems Group Leader
Fast Reactors Group Leader
Researcher
Researcher
Journal papers and patents
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.Teaching & PhD
PhD Students
Diego Mondaray Muñoz, Alessio Rossi
Past EPFL PhD Students
Rodrigo Gonzalez Gonzaga De Oliveira, Janos Bodi, Mohamed Aly Hashem Mohamed Sayed, Vincenzo Anthony Di Nora