Helmholtz-Zentrum Dresden-Rossendorf

Reactor Safety

Dr. Emil Fridman
Phone:+49 351 260 - 2167
Email: e.fridmanAthzdr.de
Links:List of publications
ResearchGate
Address for visitors:Bautzner Landstraße 400
01328 Dresden
Postal address:POB 51 01 19
01314 Dresden
Germany

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

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.
Corresponding author: Rohde, Ulrich HZDR

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-Link: http://dx.doi.org/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 LogoScience 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 LogoScience and Technology of Nuclear Installations 2009(2009), 940286