Personal web page of Emil Fridman
Scientific career
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Since 2015:Senior Scientist, Reactor Safety Division, Institute of Resource Ecology, HZDR.
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2012-2014:Head, Junior Research Group Reactor Physics, Institute of Resource Ecology, HZDR.
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2008-2011:Research Assistant, Institute of Safety Research, HZDR.
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2004-2008:Ben-Gurion University, Ph.D. in Nuclear Engineering.
Research fields
- Reactor physics and engineering,
- Advanced nuclear fuel cycles,
- Safety analysis of nuclear reactors,
- Nuclear waste management.
Projects
- 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.
- 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.
- IAEA CRP T12026 , Coordinated Research Project on Near term and Promising Long Term Options for Deployment of Thorium Based Nuclear Energy, 2011-2016.
- FP7 FREYA: Fast Reactor Experiments for hYbrid Applications, 2011-2016.
- FP7 CP-ESFR: Collaborative Project on European Sodium Fast reactor, 2009-2012.
Publications
2021
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.; Nikitin, E.; Bilodid, Y.; Mikityuk, K.
Related publications
- Optimization of multi-group energy structures for … (Id 31706) HZDR-primary research data are used by this (Id 31688) publication
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Annals of Nuclear Energy 155(2021), 108183
DOI: 10.1016/j.anucene.2021.108183
Neutronic analysis of the European Sodium Fast Reactor: Part II - burnup results
Fridman, E.; 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.
Related publications
- ESFR-SMART WP1.2.1 dataset (Id 31102) HZDR-primary research data are used by this (Id 31098) publication
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Journal of Nuclear Engineering and Radiation Science (2021)
DOI: 10.1115/1.4048765
Neutronic analysis of the European Sodium Fast Reactor: Part I - fresh core results
Fridman, E.; 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.
Related publications
- ESFR-SMART WP1.2.1 dataset (Id 31102) HZDR-primary research data are used by this (Id 31097) publication
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Journal of Nuclear Engineering and Radiation Science (2021)
DOI: 10.1115/1.4048905
Evaluation of the ESFR End of Cycle State and Detailed Spatial Distributions of Reactivity Coefficients
Davies, U.; Margulis, M.; Shwageraus, E.; Fridman, E.; Garcia-Herranz, N.; Jimenez-Carrascosa, A.; Cabellos, O.; Gregg, R.
Related publications
- ESFR-SMART WP1.2.1 dataset (Id 31102) HZDR-primary research data are used by this (Id 29935) publication
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Contribution to 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
2020
Dynamic simulation of the CEFR control rod drop experiments with the Monte Carlo code Serpent
Related publications
- Dataset for dynamic simulation of the CEFR control rod … (Id 31104) 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
X2 VVER-1000 benchmark revision: fresh HZP core state and the reference Monte Carlo solution
Bilodid, Y.; Fridman, E.; Lötsch, T.
Related publications
- X2 benchmark specification dataset (Id 30009) is a supplement to this (Id 29992) publication
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Annals of Nuclear Energy 144(2020), 107558
DOI: 10.1016/j.anucene.2020.107558
Nuclear Data Sensitivity and Uncertainty Analysis of Critical VENUS-F Cores with the Serpent Monte Carlo Code
Fridman, E.; Valtavirta, V.; Aufiero, M.
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Annals of Nuclear Energy 138(2020), 107196
DOI: 10.1016/J.ANUCENE.2019.107196
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
DOI: 10.1115/1.4044000
2019
Modeling of the FFTF isothermal physics tests with the Serpent and DYN3D codes
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Annals of Nuclear Energy 132(2019), 679-685
DOI: 10.1016/j.anucene.2019.06.058
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.; Kotlyar, D.
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Annals of Nuclear Energy 125(2019), 291-306
DOI: 10.1016/j.anucene.2018.11.020
2018
Explicit decay heat calculation in the nodal diffusion code DYN3D
Bilodid, Y.; Fridman, E.; Kotlyar, D.; Shwageraus, E.
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Annals of Nuclear Energy 121(2018), 374-381
DOI: 10.1016/j.anucene.2018.07.045
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
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
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
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
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
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
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
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
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
DOI: 10.1016/j.anucene.2015.07.030
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
DOI: 10.1016/j.anucene.2015.06.007
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
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
DOI: 10.1016/j.anucene.2014.08.054
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
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
DOI: 10.13182/NSE14-59
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
DOI: 10.1016/j.anucene.2014.05.018
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
DOI: 10.1016/j.anucene.2014.05.017
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
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
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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Contribution to 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
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
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
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)
DOI: 10.1016/j.anucene.2012.11.030
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
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
DOI: 10.1016/j.nucengdes.2011.09.051
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
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
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
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.
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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.
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Science and Technology of Nuclear Installations 2009(2009), 940286