Takip et
Emil Fridman
Emil Fridman
HZDR
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Başlık
Alıntı yapanlar
Alıntı yapanlar
Yıl
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
1902011
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
1612016
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
1532016
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
1362014
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
852011
Modeling of SFR cores with Serpent–DYN3D codes sequence
E Fridman, E Shwageraus
Annals of Nuclear Energy 53, 354-363, 2013
842013
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
752011
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
742015
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
742013
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
592010
ESFR-SMART: new Horizon-2020 project on SFR safety
K Mikityuk, J Krepel, E Girardi
582017
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
572015
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
422020
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
422008
Implementation of multi-group cross-section methodology in BGCore MC-depletion code
E Fridman, E Shwageraus, A Galperin
392008
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
382015
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
37*2012
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
322014
Sensitivity study on Xe depletion in the high burn-up structure of UO2
L Holt, A Schubert, P Van Uffelen, CT Walker, E Fridman, T Sonoda
Journal of Nuclear Materials 452 (1-3), 166-172, 2014
312014
Revised methods for few-group cross section generation in the Serpent Monte Carlo code
E Fridman, J Leppänen
Proceeding of the PHYSOR 2012, 2012
302012
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