Analysis of loss of flow without scram test in the FFTF reactor – Part II: System thermal hydraulics with point neutron kinetics

Ponomarev, A.; Nikitin, E.; Fridman, E.

Verknüpfte Publikationen

• Analysis of loss of flow without scram test in the FFTF reactor – Part I …
  ROBIS: 37345 has this (Id 37346) publication as part
• Data publication: Analysis of loss of flow without scram test in the FFTF …
  ROBIS: 38758 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 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 HZDR-primary research data are used by this (Id 37346) publication

• Progress in Nuclear Energy 170(2024), 105130
  DOI: 10.1016/j.pnucene.2024.105130

Analysis of loss of flow without scram test in the FFTF reactor – Part I: preparation of neutronics data

Nikitin, E.; Fridman, E.; Ponomarev, A.

Verknüpfte Publikationen

• Analysis of loss of flow without scram test in the FFTF reactor – Part II …
  ROBIS: 37346 is part of this (Id 37345) publication
• Data publication: Analysis of loss of flow without scram test in the FFTF …
  ROBIS: 38370 HZDR-primary research data are used by this (Id 37345) publication

• Progress in Nuclear Energy 168(2024), 105018
  Online First (2023) DOI: 10.1016/j.pnucene.2023.105018
  Cited 2 times in Scopus

CEFR control rod drop transient simulation using RAST-F code system

Tran, T. Q.; Huo, X.; Fridman, E.; Lee, D.

Verknüpfte Publikationen

• Dataset for dynamic simulation of the CEFR control rod drop experiments
  RODARE: 354 HZDR-primary research data are used by this (Id 37426) publication

• Nuclear Engineering and Technology (2023)
  DOI: 10.1016/j.net.2023.08.017

Coupled 3D neutronics/thermal-hydraulics analysis of Superphénix start-up tests with DYN3D/ATHLET code system

Ponomarev, A.; Nikitin, E.; Fridman, E.

• Nuclear Engineering and Design 412(2023), 112456
  DOI: 10.1016/j.nucengdes.2023.112456
  Cited 3 times in Scopus

Definition of the neutronics benchmark of the NuScale-like core

Fridman, E.; Bilodid, Y.; Valtavirta, V.

Verknüpfte Publikationen

• RODARE: 2208 HZDR-primary research data are used by this (Id 37135) publication

• Nuclear Engineering and Technology 55(2023)10, 3639-3647
  DOI: 10.1016/j.net.2023.06.029
  Cited 5 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.; Krepel, J.; Lavarenne, J.; Mikityuk, K.; Nikitin, E.; Ponomarev, A.; Radman, S.; Shwageraus, E.; Tollit, B.

Verknüpfte Publikationen

• Data publication: ESFR-SMART T1.2.4
  ROBIS: 36609 HZDR-primary research data are used by this (Id 36608) publication

• Journal of Nuclear Engineering and Radiation Science 9(2023)3, 031301
  DOI: 10.1115/1.4056930
  Cited 3 times in Scopus

Extension of the DYN3D/ATHLET code system to SFR applications: models description and initial validation

Fridman, E.; Nikitin, E.; Ponomarev, A.; Di Nora, A.; Kliem, S.; Mikityuk, K.

Verknüpfte Publikationen

• Phenix EOL natural convection test: Serpent/DYN3D/ATHLET I/O data
  RODARE: 2007 HZDR-primary research data are used by this (Id 35760) publication

• Annals of Nuclear Energy 182(2023), 109619
  Online First (2022) DOI: 10.1016/j.anucene.2022.109619
  Cited 7 times in Scopus

Superphénix Benchmark Part II: Transient Results

Ponomarev, A.; Mikityuk, K.; Fridman, E.; Di Nora, V. A.; Bubelis, E.; Schikorr, M.

Verknüpfte Publikationen

• SPX-StartUp-ATHLET-StandAlone
  ROBIS: 32430 HZDR-primary research data are used by this (Id 32428) publication

• Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011321
  Online First (2021) DOI: 10.1115/1.4051877
  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.; Gregg, R.

Verknüpfte Publikationen

• ESFR-SMART WP1.2.2 dataset - DecayHeat
  ROBIS: 32432 HZDR-primary research data are used by this (Id 32427) publication

• Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011319
  Online First (2021) DOI: 10.1115/1.4051798
  Cited 3 times in Scopus

Superphénix Benchmark Part I: Results of Static neutronics

Ponomarev, A.; Mikityuk, K.; Zhang, L.; Nikitin, E.; Fridman, E.; Álvarez-Velarde, F.; Romojaro-Otero, P.; Jiménez-Carrascosa, A.; García-Herranz, N.; Lindley, B.; Davies, U.; Seubert, A.; Henry, R.

Verknüpfte Publikationen

• SPX Benchmark Part I: Results of Static neutronics -- HZDR results
  ROBIS: 32433 HZDR-primary research data are used by this (Id 32426) publication

• Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011320
  Online First (2021) DOI: 10.1115/1.4051449
  Cited 10 times in Scopus

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.

Verknüpfte Publikationen

• ESFR-SMART WP1.2.1 dataset
  ROBIS: 31102 HZDR-primary research data are used by this (Id 31098) publication

• Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011302
  Online First (2021) DOI: 10.1115/1.4048765
  Cited 8 times in Scopus

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.

Verknüpfte Publikationen

• ESFR-SMART WP1.2.1 dataset
  ROBIS: 31102 HZDR-primary research data are used by this (Id 31097) publication

• Journal of Nuclear Engineering and Radiation Science 8(2022)1, 011301
  Online First (2021) DOI: 10.1115/1.4048905
  Cited 9 times in Scopus

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.; Nikitin, E.; Bilodid, Y.; Mikityuk, K.

Verknüpfte Publikationen

• Optimization of multi-group energy structures for diffusion analyses of …
  ROBIS: 31706 HZDR-primary research data are used by this (Id 32640) publication

• Annals of Nuclear Energy 163(2021), 108541
  DOI: 10.1016/j.anucene.2021.108541
  Cited 1 times in Scopus

Neutronic Modelling of the FFTF Control Rod Worth Measurements with Diffusion Codes

Nikitin, E.; Fridman, E.; Mikityuk, K.; Radman, S.; Fiorina, C.

Verknüpfte Publikationen

• FFTF startup tests - joint publication raw data
  ROBIS: 32446 HZDR-primary research data are used by this (Id 32445) publication

• 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
  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.; Jiménez-Carrascosa, A.; García-Herranz, N.; Cabellos, O.; Gregg, R.; Krepel, J.

Verknüpfte Publikationen

• ESFR-SMART WP1.2.1 dataset
  ROBIS: 31102 HZDR-primary research data are used by this (Id 32429) publication

• Journal of Nuclear Engineering and Radiation Science 8(2021)1, 011316
  DOI: 10.1115/1.4052121
  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.; Nikitin, E.; Bilodid, Y.; Mikityuk, K.

Verknüpfte Publikationen

• Optimization of multi-group energy structures for diffusion analyses of …
  ROBIS: 31706 HZDR-primary research data are used by this (Id 31688) publication

• Annals of Nuclear Energy 155(2021), 108183
  DOI: 10.1016/j.anucene.2021.108183
  Cited 6 times in Scopus

Modelling ASTRID-Like Sodium-Cooled Fast Reactor with Serpent DYN3D Code Sequence

Rydlewicz, W.; Fridman, E.; Shwageraus, E.

Verknüpfte Publikationen

• Data: ASTRID-DYN3D
  ROBIS: 32353 HZDR-primary research data are used by this (Id 29937) publication

• 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

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.

Verknüpfte Publikationen

• ESFR-SMART WP1.2.1 dataset
  ROBIS: 31102 HZDR-primary research data are used by this (Id 29935) publication

• 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
  Cited 1 times in Scopus

Dynamic simulation of the CEFR control rod drop experiments with the Monte Carlo code Serpent

Fridman, E.; Huo, X.

Verknüpfte Publikationen

• Dataset for dynamic simulation of the CEFR control rod drop experiments
  ROBIS: 31104 HZDR-primary research data are used by this (Id 31096) publication

• Annals of Nuclear Energy 148(2020), 107707
  DOI: 10.1016/j.anucene.2020.107707
  Cited 9 times in Scopus

X2 VVER-1000 benchmark revision: fresh HZP core state and the reference Monte Carlo solution

Bilodid, Y.; Fridman, E.; Lötsch, T.

Verknüpfte Publikationen

• X2 benchmark specification dataset
  ROBIS: 30009 HZDR-primary research data are used by this (Id 29992) publication

• Annals of Nuclear Energy 144(2020), 107558
  DOI: 10.1016/j.anucene.2020.107558
  Cited 28 times in Scopus

Nuclear Data Sensitivity and Uncertainty Analysis of Critical VENUS-F Cores with the Serpent Monte Carlo Code

Fridman, E.; Valtavirta, V.; Aufiero, M.

• Annals of Nuclear Energy 138(2020), 107196
  Online First (2019) DOI: 10.1016/J.ANUCENE.2019.107196
  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.

• Journal of Nuclear Engineering and Radiation Science 6(2020)1, 011402
  Online First (2019) DOI: 10.1115/1.4044000
  Cited 1 times in Scopus

Modeling of the FFTF isothermal physics tests with the Serpent and DYN3D codes

Nikitin, E.; Fridman, E.

• Annals of Nuclear Energy 132(2019), 679-685
  DOI: 10.1016/j.anucene.2019.06.058
  ISSN: 0306-4549
  Cited 12 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.; Kotlyar, D.

• Annals of Nuclear Energy 125(2019), 291-306
  Online First (2018) DOI: 10.1016/j.anucene.2018.11.020
  Cited 5 times in Scopus

Explicit decay heat calculation in the nodal diffusion code DYN3D

Bilodid, Y.; Fridman, E.; Kotlyar, D.; Shwageraus, E.

• Annals of Nuclear Energy 121(2018), 374-381
  DOI: 10.1016/j.anucene.2018.07.045
  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.

• Annals of Nuclear Energy 119(2018), 390-395
  DOI: 10.1016/j.anucene.2018.05.017
  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.

• Annals of Nuclear Energy 119(2018), 411-418
  DOI: 10.1016/j.anucene.2018.05.016
  Cited 16 times in Scopus

Extension of the reactor dynamics code DYN3D to SFR applications – Part I: thermal expansion models

Nikitin, E.; Fridman, E.

• Annals of Nuclear Energy 119(2018), 382-389
  DOI: 10.1016/j.anucene.2018.05.015
  Cited 19 times in Scopus

Modeling of FREYA Fast Critical Experiments with the Serpent Monte Carlo Code

Fridman, E.; Kochetkov, A.; Krása, A.

• Annals of Nuclear Energy 108(2017), 239-252
  DOI: 10.1016/j.anucene.2017.04.045
  Cited 12 times in Scopus

Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code

Leppanen, J.; Pusa, M.; Fridman, E.

• Annals of Nuclear Energy 96(2016), 126-136
  DOI: 10.1016/j.anucene.2016.06.007
  Cited 107 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.

• Progress in Nuclear Energy 89(2016), 170-190
  DOI: 10.1016/j.pnucene.2016.02.013
  Cited 119 times in Scopus

Hybrid microscopic depletion model in nodal code DYN3D

Bilodid, Y.; Kotlyar, D.; Shwageraus, E.; Fridman, E.; Kliem, S.

• Annals of Nuclear Energy 92(2016), 397-406
  DOI: 10.1016/j.anucene.2016.02.012
  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.

• Annals of Nuclear Energy 87(2016)2, 517-526
  DOI: 10.1016/j.anucene.2015.10.006
  Cited 8 times in Scopus

Feasibility assessment of the once-through Thorium fuel cycle for the PTVM LWR concept

Rachamin, R.; Fridman, E.; Galperin, A.

• Annals of Nuclear Energy 85(2015), 1119-1130
  DOI: 10.1016/j.anucene.2015.07.030
  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.

• Annals of Nuclear Energy 85(2015), 544-551
  DOI: 10.1016/j.anucene.2015.06.007
  Cited 38 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.

• Annals of Nuclear Energy 81(2015), 34-40
  DOI: 10.1016/j.anucene.2015.03.030
  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.

• Annals of Nuclear Energy 75(2015), 492-497
  Online First (2014) DOI: 10.1016/j.anucene.2014.08.054
  Cited 52 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.

• Annals of Nuclear Energy 75(2015), 249-260
  DOI: 10.1016/j.anucene.2014.07.044
  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.

• Nuclear Science and Engineering 179(2015)3
  DOI: 10.13182/NSE14-59
  Cited 4 times in Scopus

High Conversion Th-U233 fuel for current generation of PWRs: Part II – 3D full core analysis

Baldova, D.; Fridman, E.; Shwageraus, E.

• Annals of Nuclear Energy 73(2014), 560-566
  DOI: 10.1016/j.anucene.2014.05.018
  Cited 14 times in Scopus

High Conversion Th-U233 fuel for current generation of PWRs: Part I – assembly level analysis

Baldova, D.; Fridman, E.; Shwageraus, E.

• Annals of Nuclear Energy 73(2014), 552-559
  DOI: 10.1016/j.anucene.2014.05.017
  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.

• Journal of Nuclear Materials 452(2014), 166-172
  DOI: 10.1016/j.jnucmat.2014.05.009
  Cited 16 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.

• Annals of Nuclear Energy 65(2014), 272-279
  DOI: 10.1016/j.anucene.2013.10.032
  Cited 97 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.

• 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
  Cited 4 times in Scopus

Axial discontinuity factors for the nodal diffusion analysis of high conversion BWR cores

Fridman, E.; Duerigen, S.; Bilodid, Y.; Kotlyar, D.; Shwageraus, E.

• Annals of Nuclear Energy 62(2013), 129-136
  DOI: 10.1016/j.anucene.2013.06.006
  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.

• Annals of Nuclear Energy 60(2013), 248-255
  DOI: 10.1016/j.anucene.2013.05.011
  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.

• Annals of Nuclear Energy 55(2013)
  DOI: 10.1016/j.anucene.2012.11.030
  Cited 58 times in Scopus

Modeling of SFR cores with Serpent-DYN3D codes sequence

Fridman, E.; Shwageraus, E.

• Annals of Nuclear Energy 53(2013), 354-363
  DOI: 10.1016/j.anucene.2012.08.006
  Cited 54 times in Scopus

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.

• Nuclear Engineering and Design 251(2012), 412-422
  Online First (2011) DOI: 10.1016/j.nucengdes.2011.09.051
  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

Coupled neutronic thermo-hydraulic analysis of full PWR core with Monte-Carlo based BGCore system

Kotlyar, D.; Shaposhnik, Y.; Fridman, E.; Shwageraus, E.

• Nuclear Engineering and Design 241(2011)9, 3777-3786
  DOI: 10.1016/j.nucengdes.2011.07.028
  Cited 69 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.

• Annals of Nuclear Energy 38(2011)6, 1399-1405
  DOI: 10.1016/j.anucene.2011.01.032
  Cited 104 times in Scopus

Pu recycling in a full Th-MOX PWR core: Part I - steady state analysis

Fridman, E.; Kliem, S.

• Nuclear Engineering and Design 241(2011)1, 193-202
  DOI: 10.1016/j.nucengdes.2010.10.036
  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

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

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