Helmholtz-Zentrum Dresden-Rossendorf

Reactor Safety

Dr. Emil Fridman
Phone:+49 351 260 2167
Email: e.fridmanAthzdr.de
Links:List of publications
ResearchGate
ORCID: 0000-0002-4468-5238
AddressBautzner Landstraße 400
01328 Dresden
Building/Office:250/209

Scientific career

  • Since 2015:
    Senior Scientist, Reactor Safety Division, Institute of Resource Ecology, HZDR.
  • 2012-2014:
    Head, Junior Research Group Reactor Physics, Institute of Resource Ecology, HZDR.
  • 2008-2011:
    Research Assistant, Institute of Safety Research, HZDR.
  • 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

Publications

2020

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


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


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

Fridman, E.; Huo, X.

Related publications


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

Bilodid, Y.; Fridman, E.; Lötsch, T.

Related publications


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

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


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

2019

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

Nikitin, E.; Fridman, E.


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.


2018

Explicit decay heat calculation in the nodal diffusion code DYN3D

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


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.


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.


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

Nikitin, E.; Fridman, E.


2017

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

Fridman, E.; Kochetkov, A.; Krása, A.


2016

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

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


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.


Hybrid microscopic depletion model in nodal code DYN3D

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


High Conversion Th–U233 fuel for current generation of PWRs: Part III – Fuel availability and utilization considerations

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


2015

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

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


On the use of the SPH method in nodal diffusion analyses of SFR cores

Nikitin, E.; Fridman, E.; Mikityuk, K.


Spectral history model in DYN3D: Verification against coupled Monte-Carlo thermal-hydraulic code BGCore

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


Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems

Nikitin, E.; Fridman, E.; Mikityuk, K.


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.


One-Group Cross-Section Generation for Monte Carlo Burnup Codes: Multigroup Method Extension and Verification

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


2014

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

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


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

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


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.


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.


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

2013

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

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


Design and analysis of an innovative pressure tubes light water reactor with variable moderator control

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


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.


Modeling of SFR cores with Serpent-DYN3D codes sequence

Fridman, E.; Shwageraus, E.


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.


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.


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.


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

Fridman, E.; Kliem, S.


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.

  • Open Access Logo 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.

  • Open Access Logo Science and Technology of Nuclear Installations 2009(2009), 940286

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