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

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

Related publications

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

• Contribution to 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

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

• 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

• 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

• Journal of Nuclear Engineering and Radiation Science (2021)
  DOI: 10.1115/1.4048905

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

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

Related publications

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

• Contribution to 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.

Related publications

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

• 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

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

Fridman, E.; Huo, X.

Related publications

• Dataset for dynamic simulation of the CEFR control rod … (Id 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

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

• 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.

• 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.

• Journal of Nuclear Engineering and Radiation Science 6(2020)1, 011402
  DOI: 10.1115/1.4044000

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

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
  DOI: 10.1016/j.anucene.2018.11.020

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

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

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

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

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

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

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

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

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

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

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

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

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
  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.

• 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.

• Nuclear Science and Engineering 179(2015)3
  DOI: 10.13182/NSE14-59

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

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

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

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

Extension and application of the reactor dynamics code DYN3D for Block-type High Temperature Reactors

Baier, S.; Fridman, E.; Kliem, S.; Rohde, U.

• 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

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

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

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

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

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
  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

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

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

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

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