| Heat transfer to liquid metal: review of data and correlations for tube bundles K Mikityuk Nuclear Engineering and Design 239 (4), 680-687, 2009 | 336 | 2009 |
| GeN-Foam: a novel OpenFOAM® based multi-physics solver for 2D/3D transient analysis of nuclear reactors C Fiorina, I Clifford, M Aufiero, K Mikityuk Nuclear Engineering and Design 294, 24-37, 2015 | 189 | 2015 |
| The core design of ALFRED, a demonstrator for the European lead-cooled reactors G Grasso, C Petrovich, D Mattioli, C Artioli, P Sciora, D Gugiu, G Bandini, ... Nuclear Engineering and Design 278, 287-301, 2014 | 178 | 2014 |
| FAST: An advanced code system for fast reactor transient analysis K Mikityuk, S Pelloni, P Coddington, E Bubelis, R Chawla Annals of Nuclear Energy 32 (15), 1613-1631, 2005 | 105 | 2005 |
| Investigation of the MSFR core physics and fuel cycle characteristics C Fiorina, M Aufiero, A Cammi, F Franceschini, J Krepel, L Luzzi, ... Progress in Nuclear Energy 68, 153-168, 2013 | 94 | 2013 |
| A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code G Khvostov, K Mikityuk, MA Zimmermann Nuclear Engineering and Design 241 (8), 2983-3007, 2011 | 83 | 2011 |
| Gas cooled fast reactor research in Europe R Stainsby, K Peers, C Mitchell, C Poette, K Mikityuk, J Somers Nuclear Engineering and Design 241 (9), 3481-3489, 2011 | 80 | 2011 |
| Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems E Nikitin, E Fridman, K Mikityuk Annals of Nuclear Energy 75, 492-497, 2015 | 65 | 2015 |
| Fuel cycle advantages and dynamics features of liquid fueled MSR J Křepel, B Hombourger, C Fiorina, K Mikityuk, U Rohde, S Kliem, A Pautz Annals of nuclear energy 64, 380-397, 2014 | 65 | 2014 |
| EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors J Krepel, S Pelloni, K Mikityuk, P Coddington Annals of Nuclear Energy 36 (5), 550-561, 2009 | 65 | 2009 |
| Core neutronics characterization of the GFR2400 gas cooled fast reactor Z Perkó, S Pelloni, K Mikityuk, J Křepel, M Szieberth, G Gaëtan, B Vrban, ... Progress in Nuclear Energy 83, 460-481, 2015 | 61 | 2015 |
| Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform C Fiorina, N Kerkar, K Mikityuk, P Rubiolo, A Pautz Annals of Nuclear Energy 96, 212-222, 2016 | 60 | 2016 |
| ESFR-SMART: new Horizon-2020 project on SFR safety K Mikityuk, J Krepel, E Girardi | 57 | 2017 |
| On the use of the SPH method in nodal diffusion analyses of SFR cores E Nikitin, E Fridman, K Mikityuk Annals of Nuclear Energy 85, 544-551, 2015 | 55 | 2015 |
| TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions A Chenu, K Mikityuk, R Chawla Nuclear engineering and design 239 (11), 2417-2429, 2009 | 46 | 2009 |
| Demonstrating the effectiveness of the European LFR concept: the ALFRED core design G Grasso, C Petrovich, K Mikityuk, D Mattioli, F Manni, D Gugiu International Conference on Fast Reactors and Related Fuel Cycles: Safe …, 2013 | 45 | 2013 |
| Gas-cooled fast reactor (GFR): overview and perspectives P Anzieu, R Stainsby, K Mikityuk Paris, France 9-10 September 2009 127, 2009 | 38 | 2009 |
| Pressure drop modeling and comparisons with experiments for single-and two-phase sodium flow A Chenu, K Mikityuk, R Chawla Nuclear engineering and design 241 (9), 3898-3909, 2011 | 37 | 2011 |
| Code assessment and modelling for Design Basis Accident Analysis of the European Sodium Fast Reactor design. Part I: System description, modelling and benchmarking A Lázaro, L Ammirabile, G Bandini, G Darmet, S Massara, P Dufour, ... Nuclear Engineering and Design 266, 1-16, 2014 | 35 | 2014 |
| Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle K Sun, J Krepel, K Mikityuk, S Pelloni, R Chawla Annals of Nuclear Energy 38 (7), 1645-1657, 2011 | 35 | 2011 |
