| On the use of the Serpent Monte Carlo code for few-group cross section generation E Fridman, J Leppänen Annals of Nuclear Energy 38 (6), 1399-1405, 2011 | 173 | 2011 |
| The reactor dynamics code DYN3D–models, validation and applications U Rohde, S Kliem, U Grundmann, S Baier, Y Bilodid, S Duerigen, ... Progress in Nuclear Energy 89, 170-190, 2016 | 145 | 2016 |
| Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code J Leppänen, M Pusa, E Fridman Annals of Nuclear Energy 96, 126-136, 2016 | 129 | 2016 |
| Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code J Leppänen, M Aufiero, E Fridman, R Rachamin, S van der Marck Annals of Nuclear Energy 65, 272-279, 2014 | 118 | 2014 |
| Coupled neutronic thermo-hydraulic analysis of full PWR core with Monte-Carlo based BGCore system D Kotlyar, Y Shaposhnik, E Fridman, E Shwageraus Nuclear Engineering and Design 241 (9), 3777-3786, 2011 | 83 | 2011 |
| Modeling of SFR cores with Serpent–DYN3D codes sequence E Fridman, E Shwageraus Annals of Nuclear Energy 53, 354-363, 2013 | 76 | 2013 |
| Neutronic analysis of SFR core with HELIOS-2, Serpent, and DYN3D codes R Rachamin, C Wemple, E Fridman Annals of Nuclear Energy 55, 194-204, 2013 | 71 | 2013 |
| Pu recycling in a full Th-MOX PWR core. Part I: Steady state analysis E Fridman, S Kliem Nuclear engineering and design 241 (1), 193-202, 2011 | 71 | 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 | 64 | 2015 |
| Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices E Bomboni, N Cerullo, E Fridman, G Lomonaco, E Shwageraus Nuclear Engineering and Design 240 (4), 918-924, 2010 | 59 | 2010 |
| ESFR-SMART: new Horizon-2020 project on SFR safety K Mikityuk, J Krepel, E Girardi | 56 | 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 | 54 | 2015 |
| Efficient generation of one-group cross sections for coupled Monte Carlo depletion calculations E Fridman, E Shwageraus, A Galperin Nuclear Science and Engineering 159 (1), 37-47, 2008 | 42 | 2008 |
| Implementation of multi-group cross-section methodology in BGCore MC-depletion code E Fridman, E Shwageraus, A Galperin | 40 | 2008 |
| Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor P Tusheva, E Altstadt, HG Willschütz, E Fridman, FP Weiß Annals of Nuclear Energy 75, 249-260, 2015 | 38 | 2015 |
| Development and verification of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR U Rohde, S Baier, S Duerigen, E Fridman, S Kliem, B Merk Nuclear engineering and design 251, 412-422, 2012 | 34* | 2012 |
| X2 VVER-1000 benchmark revision: Fresh HZP core state and the reference Monte Carlo solution Y Bilodid, E Fridman, T Lötsch Annals of Nuclear Energy 144, 107558, 2020 | 31 | 2020 |
| High conversion Th-U233 fuel for current generation of PWRs: Part I–Assembly level analysis D Baldova, E Fridman, E Shwageraus Annals of Nuclear Energy 73, 552-559, 2014 | 31 | 2014 |
| The use of Th in HTR: state of the art and implementation in Th/Pu fuel cycles G Mazzini, E Bomboni, N Cerullo, E Fridman, G Lomonaco, ... Science and Technology of Nuclear Installations 2009, 2009 | 28 | 2009 |
| Revised methods for few-group cross section generation in the Serpent Monte Carlo code E Fridman, J Leppänen Proceeding of the PHYSOR 2012, 2012 | 27 | 2012 |
Eugene ShwagerausUniversity of CambridgeVerified email at cam.ac.uk
