Persönliche Webseite von Emil Fridman
Dr. Emil Fridman
e.fridmanhzdr.de
Tel.: +49 351 260 2167
Wissenschaftlicher Werdegang
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Seit 2015:Wissenschaftlicher Mitarbeiter, Institut für Ressourcenökologie, HZDR.
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2012-2014:Leiter, Nachwuchsgruppe Reaktorphysik, Institut für Ressourcenökologie, HZDR.
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2008-2011:Wissenschaftlicher Mitarbeiter, Institut für Sicherheitsforschung, HZDR.
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2004-2008:Ben-Gurion Universität, Promotion in Nuclear Engineering
Forschungstätigkeit
- Reaktorphysik und -technik,
- Fortgeschrittene Kernbrennstoffzyklen,
- Sicherheitsanalysen für Kernreaktoren,
- Entsorgung von nuklearem Abfall.
Projekte
- Horizon Europe ESFR-SIMPLE: European Sodium Fast Reactor - Safety by Innovative Monitoring, Power Level flexibility
and Experimental research, 2022-2026. - Horizon 2020 McSAFER: High-Performance Monte Carlo Methods for SAFEty Demonstration, 2020-2023(1).
- Horizon 2020 McSAFE: High-Performance Monte Carlo Methods for SAFEty Demonstration, 2017-2020.
- Horizon 2020 ESFR-SMART: European Sodium Fast Reactor Safety Measures Assessment and Research Tools, 2017-2021(2).
- OECD SFR-UAM: Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of SFRs, 2015-2018.
- FP7 ESNII plus: Preparing ESNII for HORIZON 2020, 2013-2017(3).
- IAEA CRP T12026 , Coordinated Research Project on Near term and Promising Long Term Options for Deployment of Thorium Based Nuclear Energy, 2011-2016(4).
- FP7 FREYA: Fast Reactor Experiments for hYbrid Applications, 2011-2016(5).
- FP7 CP-ESFR: Collaborative Project on European Sodium Fast reactor, 2009-2012(6).
Veröffentlichungen
2024
Analysis of loss of flow without scram test in the FFTF reactor – Part II: System thermal hydraulics with point neutron kinetics
Ponomarev, A.(7); Nikitin, E.(8); Fridman, E.(9)
Verknüpfte Publikationen
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Analysis of loss of flow without scram test in the FFTF reactor – Part I …
ROBIS: 37345(10) has this (Id 37346) publication as part -
Data publication: Analysis of loss of flow without scram test in the FFTF …
ROBIS: 38370(11) HZDR-primary research data are used by this (Id 37346) publication -
Data publication: Analysis of loss of flow without scram test in the FFTF …
ROBIS: 38758(12) HZDR-primary research data are used by this (Id 37346) publication -
Data publication: Analysis of loss of flow without scram test in the FFTF …
RODARE: 2640(13) HZDR-primary research data are used by this (Id 37346) publication -
Data publication: Analysis of loss of flow without scram test in the FFTF …
RODARE: 2741(14) HZDR-primary research data are used by this (Id 37346) publication
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Progress in Nuclear Energy 170(2024), 105130
Online First (2024) DOI: 10.1016/j.pnucene.2024.105130(15)
Analysis of loss of flow without scram test in the FFTF reactor – Part I: preparation of neutronics data
Nikitin, E.(16); Fridman, E.(17); Ponomarev, A.(18)
Verknüpfte Publikationen
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Analysis of loss of flow without scram test in the FFTF reactor – Part II …
ROBIS: 37346(19) is part of this (Id 37345) publication -
Data publication: Analysis of loss of flow without scram test in the FFTF …
ROBIS: 38370(20) HZDR-primary research data are used by this (Id 37345) publication
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Progress in Nuclear Energy 168(2024), 105018
Online First (2023) DOI: 10.1016/j.pnucene.2023.105018(21)
Cited 1 times in Scopus
2023
CEFR control rod drop transient simulation using RAST-F code system
Tran, T. Q.; Huo, X.; Fridman, E.(22); Lee, D.
Verknüpfte Publikationen
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Dataset for dynamic simulation of the CEFR control rod drop experiments
ROBIS: 31104(23) HZDR-primary research data are used by this (Id 37426) publication -
Dataset for dynamic simulation of the CEFR control rod drop experiments
RODARE: 354(24) HZDR-primary research data are used by this (Id 37426) publication
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Nuclear Engineering and Technology (2023)
Online First (2023) DOI: 10.1016/j.net.2023.08.017(25)
Coupled 3D neutronics/thermal-hydraulics analysis of Superphénix start-up tests with DYN3D/ATHLET code system
Ponomarev, A.(26); Nikitin, E.(27); Fridman, E.(28)
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Nuclear Engineering and Design 412(2023), 112456
DOI: 10.1016/j.nucengdes.2023.112456(29)
Cited 3 times in Scopus
Definition of the neutronics benchmark of the NuScale-like core
Fridman, E.(30); Bilodid, Y.(31); Valtavirta, V.
Verknüpfte Publikationen
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Dataset for neutronics benchmark of NuScale-like core
ROBIS: 35855(32) HZDR-primary research data are used by this (Id 37135) publication -
Dataset for neutronics benchmark of NuScale-like core
RODARE: 2208(33) HZDR-primary research data are used by this (Id 37135) publication
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Nuclear Engineering and Technology 55(2023)10, 3639-3647
Online First (2023) DOI: 10.1016/j.net.2023.06.029(34)
Cited 2 times in Scopus
Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European SFR Core Power Distribution
Lindley, B.; Álvarez Velarde, F.; Baker, U.; Bodi, J.; Cosgrove, P.; Charles, A.; Fiorina, C.; Fridman, E.(35); Krepel, J.; Lavarenne, J.; Mikityuk, K.; Nikitin, E.(36); Ponomarev, A.; Radman, S.; Shwageraus, E.; Tollit, B.
Verknüpfte Publikationen
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Data publication: ESFR-SMART T1.2.4
ROBIS: 36609(37) HZDR-primary research data are used by this (Id 36608) publication
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Journal of Nuclear Engineering and Radiation Science 9(2023)3, 031301
Online First (2023) DOI: 10.1115/1.4056930(38)
Cited 2 times in Scopus
Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation
Fridman, E.(39); Nikitin, E.(40); Ponomarev, A.(41); Di Nora, A.; Kliem, S.(42); Mikityuk, K.
Verknüpfte Publikationen
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Phenix EOL natural convection test: Serpent/DYN3D/ATHLET I/O data
ROBIS: 35779(43) HZDR-primary research data are used by this (Id 35760) publication -
Phenix EOL natural convection test: Serpent/DYN3D/ATHLET I/O data
RODARE: 2007(44) HZDR-primary research data are used by this (Id 35760) publication
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Annals of Nuclear Energy 182(2023), 109619
Online First (2022) DOI: 10.1016/j.anucene.2022.109619(45)
Cited 5 times in Scopus
2022
Superphénix Benchmark Part II: Transient Results
Ponomarev, A.; Mikityuk, K.; Fridman, E.(46); Di Nora, V. A.; Bubelis, E.; Schikorr, M.
Verknüpfte Publikationen
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SPX-StartUp-ATHLET-StandAlone
ROBIS: 32430(47) HZDR-primary research data are used by this (Id 32428) publication
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Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011321
Online First (2021) DOI: 10.1115/1.4051877(48)
Cited 5 times in Scopus
Decay heat characterization for the European Sodium Fast Reactor
Jiménez-Carrascosa, A.; García-Herranz, N.; Krepel, J.; Margulis, M.; Davies, U.; Shwageraus, E.; Fridman, E.(49); Gregg, R.
Verknüpfte Publikationen
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ESFR-SMART WP1.2.2 dataset - DecayHeat
ROBIS: 32432(50) HZDR-primary research data are used by this (Id 32427) publication
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Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011319
Online First (2021) DOI: 10.1115/1.4051798(51)
Cited 3 times in Scopus
Superphénix Benchmark Part I: Results of Static neutronics
Ponomarev, A.; Mikityuk, K.; Zhang, L.; Nikitin, E.(52); Fridman, E.(53); Álvarez-Velarde, F.; Romojaro-Otero, P.; Jiménez-Carrascosa, A.; García-Herranz, N.; Lindley, B.; Davies, U.; Seubert, A.; Henry, R.
Verknüpfte Publikationen
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SPX Benchmark Part I: Results of Static neutronics -- HZDR results
ROBIS: 32433(54) HZDR-primary research data are used by this (Id 32426) publication
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Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011320
Online First (2021) DOI: 10.1115/1.4051449(55)
Cited 10 times in Scopus
Neutronic analysis of the European Sodium Fast Reactor: Part II - burnup results
Fridman, E.(56); Álvarez-Velarde, F.; Romojaro-Otero, P.; Tsige-Tamirat, H.; Jiménez-Carrascosa, A.; García-Herranz, N.; Bernard, F.; Gregg, R.; Krepel, J.; Massara, S.; Poumerouly, S.; Girardi, E.; Mikityuk, K.
Verknüpfte Publikationen
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ESFR-SMART WP1.2.1 dataset
ROBIS: 31102(57) HZDR-primary research data are used by this (Id 31098) publication
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Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011302
Online First (2021) DOI: 10.1115/1.4048765(58)
Cited 8 times in Scopus
Neutronic analysis of the European Sodium Fast Reactor: Part I - fresh core results
Fridman, E.(59); Álvarez-Velarde, F.; Romojaro-Otero, P.; Tsige-Tamirat, H.; Jiménez-Carrascosa, A.; García-Herranz, N.; Bernard, F.; Gregg, R.; Krepel, J.; Massara, S.; Poumerouly, S.; Girardi, E.; Mikityuk, K.
Verknüpfte Publikationen
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ESFR-SMART WP1.2.1 dataset
ROBIS: 31102(60) HZDR-primary research data are used by this (Id 31097) publication
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Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011301
Online First (2021) DOI: 10.1115/1.4048905(61)
Cited 9 times in Scopus
2021
Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part II: methodology application
Di Nora, V. A.; Fridman, E.(62); Nikitin, E.(63); Bilodid, Y.(64); Mikityuk, K.
Verknüpfte Publikationen
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Optimization of multi-group energy structures for diffusion analyses of …
ROBIS: 31706(65) HZDR-primary research data are used by this (Id 32640) publication
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Annals of Nuclear Energy 163(2021), 108541
DOI: 10.1016/j.anucene.2021.108541(66)
Cited 1 times in Scopus
Neutronic Modelling of the FFTF Control Rod Worth Measurements with Diffusion Codes
Nikitin, E.(67); Fridman, E.(68); Mikityuk, K.(69); Radman, S.(70); Fiorina, C.(71)
Verknüpfte Publikationen
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FFTF startup tests - joint publication raw data
ROBIS: 32446(72) HZDR-primary research data are used by this (Id 32445) publication
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Beitrag zu Proceedings
Physics of Reactors PHYSOR 2020, 29.03.-02.04.2020, Cambridge, United Kingdom, 978-1-5272-6447-2 -
European Physical Journal Web of Conferences 247(2021), 10017
DOI: 10.1051/epjconf/202124710017(73)
Cited 1 times in Scopus
Evaluation of the ESFR End of Equilibrium Cycle State: Spatial Distributions of Reactivity Coefficients
Baker, U.; Margulis, M.; Shwageraus, E.; Fridman, E.(74); Jiménez-Carrascosa, A.; García-Herranz, N.; Cabellos, O.; Gregg, R.; Krepel, J.
Verknüpfte Publikationen
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ESFR-SMART WP1.2.1 dataset
ROBIS: 31102(75) HZDR-primary research data are used by this (Id 32429) publication
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Journal of Nuclear Engineering and Radiation Science 8(2021)1, 011316
Online First (2021) DOI: 10.1115/1.4052121(76)
Cited 5 times in Scopus
Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part I: methodology demonstration
Di Nora, V. A.; Fridman, E.(77); Nikitin, E.; Bilodid, Y.(78); Mikityuk, K.
Verknüpfte Publikationen
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Optimization of multi-group energy structures for diffusion analyses of …
ROBIS: 31706(79) HZDR-primary research data are used by this (Id 31688) publication
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Annals of Nuclear Energy 155(2021), 108183
Online First (2021) DOI: 10.1016/j.anucene.2021.108183(80)
Cited 6 times in Scopus
Modelling ASTRID-Like Sodium-Cooled Fast Reactor with Serpent DYN3D Code Sequence
Rydlewicz, W.; Fridman, E.(81); Shwageraus, E.
Verknüpfte Publikationen
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ASTRID-DYN3D
ROBIS: 32353(82) HZDR-primary research data are used by this (Id 29937) publication
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Beitrag zu Proceedings
Physics of Reactors PHYSOR 2020, 29.03.-02.04.2020, Cambridge, United Kingdom, 978-1-5272-6447-2 -
European Physical Journal Web of Conferences 247(2021), 02028
DOI: 10.1051/epjconf/202124702028(83)
Evaluation of the ESFR End of Cycle State and Detailed Spatial Distributions of Reactivity Coefficients
Davies, U.; Margulis, M.; Shwageraus, E.; Fridman, E.(84); Garcia-Herranz, N.; Jimenez-Carrascosa, A.; Cabellos, O.; Gregg, R.
Verknüpfte Publikationen
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ESFR-SMART WP1.2.1 dataset
ROBIS: 31102(85) HZDR-primary research data are used by this (Id 29935) publication
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Beitrag zu Proceedings
Physics of Reactors PHYSOR 2020, 29.03.-02.04.2020, Cambridge, United Kingdom -
European Physical Journal Web of Conferences 247(2021), 02001
DOI: 10.1051/epjconf/202124702001(86)
Cited 1 times in Scopus
2020
Dynamic simulation of the CEFR control rod drop experiments with the Monte Carlo code Serpent
Fridman, E.(87); Huo, X.
Verknüpfte Publikationen
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Dataset for dynamic simulation of the CEFR control rod drop experiments
ROBIS: 31104(88) HZDR-primary research data are used by this (Id 31096) publication
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Annals of Nuclear Energy 148(2020), 107707
DOI: 10.1016/j.anucene.2020.107707(89)
Cited 9 times in Scopus
X2 VVER-1000 benchmark revision: fresh HZP core state and the reference Monte Carlo solution
Bilodid, Y.(90); Fridman, E.(91); Lötsch, T.
Verknüpfte Publikationen
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X2 benchmark specification dataset
ROBIS: 30009(92) HZDR-primary research data are used by this (Id 29992) publication
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Annals of Nuclear Energy 144(2020), 107558
DOI: 10.1016/j.anucene.2020.107558(93)
Cited 24 times in Scopus
Nuclear Data Sensitivity and Uncertainty Analysis of Critical VENUS-F Cores with the Serpent Monte Carlo Code
Fridman, E.(94); Valtavirta, V.; Aufiero, M.
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Annals of Nuclear Energy 138(2020), 107196
Online First (2019) DOI: 10.1016/J.ANUCENE.2019.107196(95)
Cited 3 times in Scopus
Neutronic analyses of the FREYA experiments in support of the ALFRED LFR core design and licensing
Sarotto, M.; Firpo, G.; Kochetkov, A.; Krása, A.; Fridman, E.; Cetnar, J.; Domanska, G.
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Journal of Nuclear Engineering and Radiation Science 6(2020)1, 011402
Online First (2019) DOI: 10.1115/1.4044000(96)
Cited 1 times in Scopus
2019
Modeling of the FFTF isothermal physics tests with the Serpent and DYN3D codes
Nikitin, E.; Fridman, E.(97)
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Annals of Nuclear Energy 132(2019), 679-685
DOI: 10.1016/j.anucene.2019.06.058(98)
ISSN: 0306-4549
Cited 11 times in Scopus
Applying the Serpent-DYN3D Code Sequence for the Decay Heat Analysis of Metallic Fuel Sodium Fast Reactor
Pereira, G.; Johnson, A. E.; Bilodid, Y.; Fridman, E.(99); Kotlyar, D.
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Annals of Nuclear Energy 125(2019), 291-306
Online First (2018) DOI: 10.1016/j.anucene.2018.11.020(100)
Cited 5 times in Scopus
2018
Explicit decay heat calculation in the nodal diffusion code DYN3D
Bilodid, Y.(101); Fridman, E.(102); Kotlyar, D.(103); Shwageraus, E.(104)
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Annals of Nuclear Energy 121(2018), 374-381
DOI: 10.1016/j.anucene.2018.07.045(105)
ISSN: 0306-4549
Cited 7 times in Scopus
Extension of the reactor dynamics code DYN3D to SFR applications – Part III: validation against the initial phase of the Phenix EOL natural convection test
Nikitin, E.; Fridman, E.
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Annals of Nuclear Energy 119(2018), 390-395
DOI: 10.1016/j.anucene.2018.05.017(106)
Cited 13 times in Scopus
Extension of the reactor dynamics code DYN3D to SFR applications – Part II: validation against the Phenix EOL control rod withdrawal tests
Nikitin, E.; Fridman, E.
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Annals of Nuclear Energy 119(2018), 411-418
DOI: 10.1016/j.anucene.2018.05.016(107)
Cited 16 times in Scopus
Extension of the reactor dynamics code DYN3D to SFR applications – Part I: thermal expansion models
Nikitin, E.; Fridman, E.
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Annals of Nuclear Energy 119(2018), 382-389
DOI: 10.1016/j.anucene.2018.05.015(108)
Cited 17 times in Scopus
2017
Modeling of FREYA Fast Critical Experiments with the Serpent Monte Carlo Code
Fridman, E.; Kochetkov, A.; Krása, A.
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Annals of Nuclear Energy 108(2017), 239-252
DOI: 10.1016/j.anucene.2017.04.045(109)
Cited 11 times in Scopus
2016
Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code
Leppanen, J.; Pusa, M.; Fridman, E.
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Annals of Nuclear Energy 96(2016), 126-136
DOI: 10.1016/j.anucene.2016.06.007(110)
Cited 94 times in Scopus
The reactor Dynamics code DYN3D – models, Validation and applications
Rohde, U.; Kliem, S.; Grundmann, U.; Baier, S.; Bilodid, Y.; Duerigen, S.; Fridman, E.; Gommlich, A.; Holt, L.; Grahn, A.; Kozmenkov, Y.; Mittag, S.
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Progress in Nuclear Energy 89(2016), 170-190
DOI: 10.1016/j.pnucene.2016.02.013(111)
Cited 111 times in Scopus
Hybrid microscopic depletion model in nodal code DYN3D
Bilodid, Y.; Kotlyar, D.; Shwageraus, E.; Fridman, E.; Kliem, S.
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Annals of Nuclear Energy 92(2016), 397-406
DOI: 10.1016/j.anucene.2016.02.012(112)
Cited 12 times in Scopus
High Conversion Th–U233 fuel for current generation of PWRs: Part III – Fuel availability and utilization considerations
Baldova, D.; Fridman, E.; Shwageraus, E.
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Annals of Nuclear Energy 87(2016)2, 517-526
DOI: 10.1016/j.anucene.2015.10.006(113)
Cited 7 times in Scopus
2015
Feasibility assessment of the once-through Thorium fuel cycle for the PTVM LWR concept
Rachamin, R.; Fridman, E.; Galperin, A.
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Annals of Nuclear Energy 85(2015), 1119-1130
Online First (2015) DOI: 10.1016/j.anucene.2015.07.030(114)
Cited 4 times in Scopus
On the use of the SPH method in nodal diffusion analyses of SFR cores
Nikitin, E.; Fridman, E.; Mikityuk, K.
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Annals of Nuclear Energy 85(2015), 544-551
Online First (2015) DOI: 10.1016/j.anucene.2015.06.007(115)
Cited 37 times in Scopus
Spectral history model in DYN3D: Verification against coupled Monte-Carlo thermal-hydraulic code BGCore
Bilodid, Y.; Kotlyar, D.; Margulis, M.; Fridman, E.; Shwageraus, E.
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Annals of Nuclear Energy 81(2015), 34-40
DOI: 10.1016/j.anucene.2015.03.030(116)
Cited 4 times in Scopus
Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems
Nikitin, E.; Fridman, E.; Mikityuk, K.
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Annals of Nuclear Energy 75(2015), 492-497
Online First (2014) DOI: 10.1016/j.anucene.2014.08.054(117)
Cited 51 times in Scopus
Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor
Tusheva, P.; Altstadt, E.; Willschütz, H.-G.; Fridman, E.; Weiß, F.-P.
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Annals of Nuclear Energy 75(2015), 249-260
DOI: 10.1016/j.anucene.2014.07.044(118)
Cited 31 times in Scopus
One-Group Cross-Section Generation for Monte Carlo Burnup Codes: Multigroup Method Extension and Verification
Kotlyar, D.; Fridman, E.; Shwageraus, E.
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Nuclear Science and Engineering 179(2015)3
Online First (2015) DOI: 10.13182/NSE14-59(119)
Cited 4 times in Scopus
2014
High Conversion Th-U233 fuel for current generation of PWRs: Part II – 3D full core analysis
Baldova, D.; Fridman, E.; Shwageraus, E.
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Annals of Nuclear Energy 73(2014), 560-566
Online First (2014) DOI: 10.1016/j.anucene.2014.05.018(120)
Cited 13 times in Scopus
High Conversion Th-U233 fuel for current generation of PWRs: Part I – assembly level analysis
Baldova, D.; Fridman, E.; Shwageraus, E.
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Annals of Nuclear Energy 73(2014), 552-559
Online First (2014) DOI: 10.1016/j.anucene.2014.05.017(121)
Cited 26 times in Scopus
Sensitivity study on Xe depletion in the high burn-up structure of UO2
Holt, L.; Schubert, A.; van Uffelen, P.; Walker, C. T.; Fridman, E.; Sonoda, T.
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Journal of Nuclear Materials 452(2014), 166-172
DOI: 10.1016/j.jnucmat.2014.05.009(122)
Cited 14 times in Scopus
Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code
Leppanen, J.; Aufiero, M.; Fridman, E.; Rachamin, R.; van der Marck, S.
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Annals of Nuclear Energy 65(2014), 272-279
DOI: 10.1016/j.anucene.2013.10.032(123)
Cited 90 times in Scopus
Extension and application of the reactor dynamics code DYN3D for Block-type High Temperature Reactors
Baier, S.; Fridman, E.; Kliem, S.; Rohde, U.
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Beitrag zu Proceedings
6th International Topical Meeting on High Temperature Reactor Technology HTR2012, 28.10.-01.11.2012, Tokyo, Japan -
Nuclear Engineering and Design 271(2014), 431-436
DOI: 10.1016/j.nucengdes.2013.12.013(124)
Cited 4 times in Scopus
2013
Axial discontinuity factors for the nodal diffusion analysis of high conversion BWR cores
Fridman, E.; Duerigen, S.; Bilodid, Y.; Kotlyar, D.; Shwageraus, E.
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Annals of Nuclear Energy 62(2013), 129-136
DOI: 10.1016/j.anucene.2013.06.006(125)
Cited 17 times in Scopus
Design and analysis of an innovative pressure tubes light water reactor with variable moderator control
Rachamin, R.; Fridman, E.; Galperin, A.
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Annals of Nuclear Energy 60(2013), 248-255
DOI: 10.1016/j.anucene.2013.05.011(126)
Cited 4 times in Scopus
Serpent Monte-Carlo Code: An Advanced Tool for Few-Group Cross Section Generation
Fridman, E.
- atw - International Journal for Nuclear Power 58(2013)3, 156-157
Neutronic analysis of SFR core with HELIOS-2, SERPENT, and DYN3D codes
Rachamin, R.; Wemple, C.; Fridman, E.
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Annals of Nuclear Energy 55(2013)
Online First (2013) DOI: 10.1016/j.anucene.2012.11.030(127)
Cited 58 times in Scopus
Modeling of SFR cores with Serpent-DYN3D codes sequence
Fridman, E.; Shwageraus, E.
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Annals of Nuclear Energy 53(2013), 354-363
DOI: 10.1016/j.anucene.2012.08.006(128)
Cited 54 times in Scopus
2012
The simplified P3 approach on a trigonal geometry of the nodal reactor code DYN3D
Duerigen, S.; Fridman, E.
- Kerntechnik 4(2012), 226-229
Development and verification of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR
Rohde, U.; Baier, S.; Duerigen, S.; Fridman, E.; Kliem, S.; Merk, B.
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Nuclear Engineering and Design 251(2012), 412-422
Online First (2011) DOI: 10.1016/j.nucengdes.2011.09.051(129)
ISSN: 0029-5493
Cited 15 times in Scopus
Use of Zirconium-Based Moderators to Enhance Feedback Coefficients in a MOX-Fueled Sodium-Cooled Fast Reactor
Merk, B.; Weiß, F.-P.; Fridman, E.; Kliem, S.
- Nuclear Science and Engineering 171(2012)2, 136-149
2011
Coupled neutronic thermo-hydraulic analysis of full PWR core with Monte-Carlo based BGCore system
Kotlyar, D.; Shaposhnik, Y.; Fridman, E.; Shwageraus, E.
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Nuclear Engineering and Design 241(2011)9, 3777-3786
DOI: 10.1016/j.nucengdes.2011.07.028(130)
Cited 68 times in Scopus
Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR
Rohde, U.; Baier, S.; Duerigen, S.; Fridman, E.; Kliem, S.; Merk, B.
- Kerntechnik 76(2011)3, 166-173
On the use of the Serpent Monte Carlo code for few-group cross section generation
Fridman, E.; Leppänen, J.
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Annals of Nuclear Energy 38(2011)6, 1399-1405
DOI: 10.1016/j.anucene.2011.01.032(131)
Cited 98 times in Scopus
Pu recycling in a full Th-MOX PWR core: Part I - steady state analysis
Fridman, E.; Kliem, S.
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Nuclear Engineering and Design 241(2011)1, 193-202
DOI: 10.1016/j.nucengdes.2010.10.036(132)
Cited 55 times in Scopus
On the use of a moderation layer to improve the safety behavior in sodium cooled fast reactors
Merk, B.; Fridman, E.; Weiß, F.-P.
- Annals of Nuclear Energy 38(2011)5, 921-929
2010
Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices
Bomboni, E.; Cerullo, N.; Fridman, E.; Lomonaco, G.; Shwageraus, E.
- Nuclear Engineering and Design 240(2010), 918-924
2009
The use of Th in HTR: state of the art and implementation in Th/Pu fuel cycles
Mazzini, G.; Bomboni, E.; Cerullo, N.; Fridman, E.; Lomonaco, G.; Shwageraus, E.
- Science and Technology of Nuclear Installations 2009(2009), 749736
Preliminary evaluation of a nuclear scenario involving innovative gas cooled reactors
Vezzoni, B.; Cerullo, N.; Forasassi, G.; Fridman, E.; Lomonaco, G.; Romanello, V.; Shwageraus, E.
- Science and Technology of Nuclear Installations 2009(2009), 940286
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