Helmholtz-Zentrum Dresden-Rossendorf

Reactor Safety

Dr. Sören Kliem

Head

Phone:+49 351 260 - 2318
Fax:+49 351 260 - 12318
Email: s.kliemAthzdr.de
AddressBautzner Landstraße 400
01328 Dresden

Scientific career

  • Seit 2010:
    Department head "Reactor Safety" at the Helmholtz-Zentrum Dresden- Rossendorf, Institute of Resource Ecology
  • 2010:
    PhD at Technical University Dresden, Faculty of Machinery Building
  • 1994-2010:
    Scientific co-worker at the Forschungszentrum Rossendorf, Institute of Safety Research
  • 1992:
    Graduated from Moscow Power Engineering Institute (MEI - Technical University)

Research work

  • Reactor dynamics
  • Nuclear reactor accident analysis
  • Coupling of neutron kinetic and thermal hydraulic codes
  • Experimental and numerical investigation of coolant mixing phenomena in pressurized water reactors

Projects

  • EU FP 7 Nuclear Reactor Safety Simulation Platform (NURESAFE) project (2013-2015)
  • OECD NEA Primary Coolant Loop Test Facility (PKL-3) Project (2012-2016)
  • Horizon 2020 McSAFE: High-Performance Monte Carlo Methods for SAFEty Demonstration, 2017-2020

Publications

2018

Neutron Noise Observations in German KWU Built PWR and Analyses with the Reactor Dynamics Code DYN3D
Rohde, U.; Seidl, M.; Kliem, S.ORC; Bilodid, Y.
Corresponding author: Kliem, Sören HZDR

2017

Testing the NURESIM platform on a PWR main steam line break benchmark
Kliem, S.ORC; Kozmenkov, Y.; Hadek, J.; Perin, Y.; Fouquet, F.; Bernard, F.; Sargeni, A.; Cuervo, D.; Sabater, A.; Sanchez-Cervera, S.; Garcia-Herranz, N.; Zerkak, O.; Ferroukhi, H.; Mala, P.
Corresponding author: Kliem, Sören HZDR

Simulation of an MSLB scenario using the 3D neutron kinetic core model Dyn3D coupled with the CFD software Trio U
Grahn, A.; Gommlich, A.; Kliem, S.; Bilodid, Y.; Kozmenkov, Y.

Validation of the DYN3D-Serpent code system for SFR cores using selected BFS experiments. Part I: Serpent calculations.
Rachamin, R.; Kliem, S.

Statistical Analysis of the Early Phase of SBO Accident for PWR
Kozmenkov, Y.; Jobst, M.; Kliem, S.; Schaefer, F.; Wilhelm, P.

2016

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.

Investigation of Feedback on Neutron Kinetics and Thermal Hydraulics from Detailed Online Fuel Behavior Modelling during a Boron Dilution Transient in a PWR with the Two-way Coupled Code System DYN3D-TRANSURANUS
Holt, L.; Rohde, U.; Kliem, S.; Baier, S.; Seidl, M.; Macían-Juan, R.

2015

Validation and verification of the coupled neutron kinetic/thermalhydraulic system code DYN3D/ATHLET
Kozmenkov, Y.; Kliem, S.; Rohde, U.

Boron dilution transient simulation analyses in a PWR with neutronics/thermal-hydraulics coupled codes in the NURISP project
Jimenez, G.; Herrero, J.; Gommlich, A.; Kliem, S.; Cuervo, D.; Jimenez, J.

Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project
Chanaron, B.; Ahnert, C.; Crouzet, N.; Sanchez, V.; Kolev, N.; Marchand, O.; Kliem, S.; Papukchiev, A.

WASA-BOSS: ATHLET-CD model for severe accident analysis for a generic KONVOI reactor
Tusheva, P.; Schäfer, F.; Kozmenkov, Y.; Kliem, S.; Hollands, T.; Trometer, A.; Buck, M.
Corresponding author: Tusheva, P.
  • Contribution to proceedings
    Jahrestagung Kerntechnik/Annual Meeting on Nuclear Technology, 05.-07.05.2015, Berlin, Germany
  • Lecture (Conference)
    Jahrestagung Kerntechnik/Annual Meeting on Nuclear Technology, 05.-07.05.2015, Berlin, Germany
  • atw - International Journal for Nuclear Power 60(2015)7, 442

Coupling of the 3D neutron kinetic core model DYN3D with the CFD software ANSYS CFX
Grahn, A.; Kliem, S.; Rohde, U.
  • Contribution to proceedings
    ASME 2014 22nd International Conference on Nuclear Engineering (ICONE22), 07.-11.07.2014, Prag, Tschechische Republik
    Proceedings of ICONE22
  • Lecture (Conference)
    ASME 2014 22nd International Conference on Nuclear Engineering (ICONE22), 07.-11.07.2014, Prag, Tschechische Republik
  • Annals of Nuclear Energy 84(2015), 197-203
    DOI-Link: http://dx.doi.org/10.1016/j.anucene.2014.12.015

2014

Implementation of a fast running full core pin power reconstruction method in DYN3D
Gomez, A.; Sanchez Espinosa, V. H.; Kliem, S.; Gommlich, A.

Assessment of accident management measures on early in-vessel station blackout sequence at VVER-1000 pressurized water reactors
Tusheva, P.; Schäfer, F.; Reinke, N.; Kamenov, A.; Mladenov, I.; Kamenov, K.; Kliem, S.

Coolant mixing experiments in the upper plenum of the ROCOM test facility
Prasser, H.-M.; Kliem, S.

Fuel cycle advantages and dynamics features of liquid fueled MSR
Krepel, J.; Hombourger, B.; Fiorina, C.; Mikityuk, K.; Rohde, U.; Kliem, S.; Pautz, A.

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

Numerical simulation of the insulation material transport in a PWR core under loss of coolant conditions
Höhne, T.; Grahn, A.; Kliem, S.; Rohde, U.; Weiss, F.-P.

Overview of major HZDR developments for fast reactor analysis
Merk, B.; Glivici-Cotruţă, V.; Duerigen, S.; Rohde, U.; Kliem, S.

2012

Research on the reactor physics and reactor safety of VVER reactors – Selected contributions to the XXIst Symposium of the Atomic Energy Research organization
Aszodi, A.; Kliem, S.
  • Kerntechnik 77(2012)4, 212-212

Study on severe accidents and countermeasures for VVER-1000 reactors using the integral code ASTEC
Tusheva, P.; Schäfer, F.; Reinke, N.; Altstadt, E.; Kliem, S.
  • Kerntechnik 77(2012)4, 271-277

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

Buoyancy driven mixing studies of natural circulation flows using ROCOM experiments and CFD
Höhne, T.; Kliem, S.; Rohde, U.

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

CFD simulation of fibre material transport in a PWR under loss of coolant conditions
Höhne, T.; Grahn, A.; Kliem, S.; Weiss, F.-P.
  • Kerntechnik 76(2011), 39-45

Development of Multi-Physics Code Systems based on the Reactor Dynamics Code DYN3D
Kliem, S.; Gommlich, A.; Grahn, A.; Rohde, U.; Schütze, J.; Frank, T.; Gomez, A.; Sanchez, V.
  • Invited lecture (Conferences)
    Fachtag der KTG: "Aktuelle Themen der Reaktorsicherheitsforschung in Deutschland", 07.-08.10.2010, Dresden, Deutschland
  • Contribution to proceedings
    Fachtag der KTG: "Aktuelle Themen der Reaktorsicherheitsforschung in Deutschland", 07.-08.10.2010, Dresden, Deutschland
    Tagungsband des Fachtages der KTG: "Aktuelle Themen der Reaktorsicherheitsforschung in Deutschland", CDROM: FZ Dresden-Rossendorf
  • Kerntechnik 76(2011)3, KT100569

Pu recycling in a full Th-MOX PWR core: Part I - steady state analysis
Fridman, E.; Kliem, S.

Burning plutonium and minimizing radioactive waste in existing PWRs
Mittag, S.; Kliem, S.

2010

Bedeutung von Experimenten für die Reaktorsicherheit
Teschendorff, V.; Glaeser, H.; Kliem, S.
  • Invited lecture (Conferences)
    Jahrestagung Kerntechnik 2009, 12.-14.05.2009, Dresden, Deutschland
  • Contribution to proceedings
    Jahrestagung Kerntechnik 2009, 12.-14.05.2009, Dresden, Deutschland
    Tagungsband der Jahrestagung Kerntechnik 2009; Fachsitzung: Thermohydraulische Experimente für Reaktoren der Generation II - III, Berlin: INFORUM GmbH
  • atw - International Journal for Nuclear Power 55(2010)03, 163-173

Experiments on slug mixing under natural circulation conditions at the ROCOM test facility using high resolution measurement technique and numerical modeling
Kliem, S.; Höhne, T.; Rohde, U.; Weiß, F.-P.
  • Lecture (Conference)
    XCFD4NRS - Experiments and CFD Codes Application to Nuclear Reactor Safety, 10.-12.09.2008, Grenoble, France
  • Contribution to proceedings
    XCFD4NRS - Experiments and CFD Codes Application to Nuclear Reactor Safety, 10.-12.09.2008, Grenoble, Frankreich
    Proceedings of the XCFD4NRS - Experiments and CFD Codes Application to Nuclear Reactor Safety, CDROM
  • Nuclear Engineering and Design 240(2010)9, 2271-2280
    DOI-Link: http://dx.doi.org/doi:10.1016/j.nucengdes.2009.11.015

Application of CFD codes in nuclear reactor safety analysis
Rohde, U.; Höhne, T.; Krepper, E.; Kliem, S.
  • Invited lecture (Conferences)
    TOPSAFE 2008, 01.-03.10.2008, Dubrovnik, Kroatia
  • Contribution to proceedings
    TOPSAFE 2008, 01.-03.10.2008, Dubrovnik, Kroatia
    CD-ROM. paper 099
  • Open Access LogoScience and Technology of Nuclear Installations 2010(2010), Article ID 198758
    DOI-Link: http://dx.doi.org/doi:10.1155/2010/198758

2009

ATWS analysis for PWR using the coupled code system DYN3D/ATHLET
Kliem, S.; Mittag, S.; Rohde, U.; Weiß, F.-P.

Simulation von ATWS-Transienten in Druckwasserreaktoren
Kliem, S.; Mittag, S.; Rohde, U.; Grundmann, U.; Weiß, F.-P.
  • Contribution to proceedings
    Jahrestagung Kerntechnik 2008, 27.-29.05.2008, Hamburg, Germany
    Tagungsband der Jahrestagung Kerntechnik 2008, CDROM, Berlin: INFORUM GmbH
  • Invited lecture (Conferences)
    Jahrestagung Kerntechnik 2008, 27.-29.05.2008, Hamburg, Germany
  • atw - International Journal for Nuclear Power 54(2009)2, 100-110

Experimental and numerical modeling of transition matrix from momentum to buoyancy-driven flow in a pressurized water reactor
Höhne, T.; Kliem, S.; Vaibar, R.
  • Contribution to proceedings
    16th International Conference on Nuclear Engineering ICONE16, 11.-15.05.2008, Orlando, USA
    CD_ROM, 48490
  • Lecture (Conference)
    16th International Conference on Nuclear Engineering ICONE16, 11.-15.05.2008, Orlando, USA
  • Journal of Engineering for Gas Turbines and Power - Transactions of the ASME 131(2009)1, 012906
    DOI-Link: http://dx.doi.org/DOI: 10.1115/1.2983137

2008

Jahrestagung Kerntechnik 2008 - Sektionsbericht Sektion: Thermo- und Fluiddynamik
Schaffrath, A.; Kliem, S.
  • atw - International Journal for Nuclear Power 53(2008)8/9, 559-561

Experimental determination of the boron concentration distribution in the primary circuit of a PWR after a postulated cold leg small break loss-of-coolant-accident with cold leg safety injection
Kliem, S.; Prasser, H.-M.; Sühnel, T.; Weiss, F.-P.; Hansen, A.

CFX simulations of ROCOM slug mixing experiments
Moretti, F.; Melideo, D.; D’Auria, F.; Höhne, T.; Kliem, S.
  • Contribution to proceedings
    15th International Conference on Nuclear Engineering (ICONE15), 22.-26.04.2007, Nagoya, Japan
    ICONE15-10461
  • Lecture (Conference)
    15th International Conference on Nuclear Engineering (ICONE15), 22.-26.04.2007, Nagoya, Japan
  • Open Access LogoJournal of Power and Energy Systems 2(2008)2, 720-733
    DOI-Link: http://dx.doi.org/10.1299/jpes.2.720

Boron Dilution Transients during natural circulation flow in PWR – experiments and CFD simulations
Höhne, T.; Kliem, S.; Rohde, U.; Weiss, F.-P.

Experiments at the mixing test facility ROCOM for benchmarking of CFD-codes
Kliem, S.; Sühnel, T.; Rohde, U.; Höhne, T.; Prasser, H.-M.; Weiß, F.-P.
  • Contribution to proceedings
    OECD/NEA & IAEA Workshop: "Benchmarking of CFD Codes for Application to Nuclear Reactor Safety", 05.-07.09.2006, Garching, Germany
    Proceedings CD-ROM paper A4-17, Issy-les-Moulineaux, France: OECD NEA
  • Lecture (Conference)
    OECD/NEA & IAEA Workshop: "Benchmarking of CFD Codes for Application to Nuclear Reactor Safety", 05.-07.09.2006, Garching, Germany
  • Nuclear Engineering and Design 238(2008), 566-576
    DOI-Link: http://dx.doi.org/10.1016/j.nucengdes.2007.02.053

2007

DYN3D - Advanced Reactor Simulations in 3D
Rohde, U.; Grundmann, U.; Kliem, S.
  • Nuclear Energy Review 2(2007), 28-30

Jahrestagung Kerntechnik - Sektionsbericht Sektion: Thermo- und Fluiddynamik
Stieglitz, R.; Kliem, S.
  • atw - International Journal for Nuclear Power 52(2007)10, 652-654

Comparative evaluation of coolant mixing experiments at the ROCOM, Vattenfall, and Gidropress test facilities
Kliem, S.; Hemström, B.; Bezrukov, Y.; Höhne, T.; Rohde, U.
  • Open Access LogoScience and Technology of Nuclear Installations 2007(2007), 25950
    DOI-Link: http://dx.doi.org/doi:10.1155/2007/25950
  • Lecture (Conference)
    Annual Meeting of the AER Working Group D, 08.-09.05.2007, Paris, France

Modeling of a Buoyancy-Driven Flow experiment in Pressurized Water Reactors using CFD-Methods
Höhne, T.; Kliem, S.
  • Open Access LogoNuclear Engineering and Technology 39(2007)4, 327-336

Qualification of coupled 3D neutron kinetic/thermal hydraulic code systems by the calculation of main steam line break benchmarks in a NPP with VVER-440 reactor
Kliem, S.; Danilin, S.; Hämäläinen, A.; Hadek, J.; Kereszturi, A.; Siltanen, P.
  • Nuclear Science and Engineering 157(2007)3, 280-298

Fluid mixing and flow distribution ín a primary circuit of a nuclear pressurized water reactor – Validation of CFD codes
Rohde, U.; Höhne, T.; Kliem, S.; Hemström, B.; Scheuerer, M.; Toppila, T.; Aszodi, A.; Boros, I.; Farkas, I.; Muehlbauer, P.; Vyskocil, V.; Klepac, J.; Remis, J.; Dury, T.

Hydrodynamic phenomena in the downcomer during flow rate transients in the primary circuit of a PWR
Cartland Glover, G. M.; Höhne, T.; Kliem, S.; Rohde, U.; Weiss, F.-P.; Prasser, H.-M.

Modeling of a buoyancy-driven flow experiment at the ROCOM test facility using the CFD-Code ANSYS CFX
Höhne, T.; Kliem, S.; Weiß, F.-P.
  • atw - International Journal for Nuclear Power 3(2007), 168-174

Calculation of the VVER-1000 Coolant Transient Benchmark using the Coupled Code Systems DYN3D/RELAP5 and DYN3D/ATHLET
Kozmenkov, Y.; Kliem, S.; Grundmann, U.; Rohde, U.; Weiss, F.-P.

Experimente an der Versuchsanlage ROCOM zur Kühlmittelvermischung bei Wiederanlauf der Naturzirkulation
Kliem, S.; Sühnel, T.; Prasser, H.-M.; Weiß, F.-P.
  • Contribution to proceedings
    KTG-Fachtag "Aktuelle Themen der Reaktorsicherheitsforschung in Deutschland", 03.-04.04.2006, Dresden, Germany
    Tagungsband FZR-455, 1437-322X, I-6
  • atw - International Journal for Nuclear Power (2007), 352-360
  • Invited lecture (Conferences)
    KTG-Fachtag "Aktuelle Themen der Reaktorsicherheitsforschung in Deutschland", 03.-04.04.2006, Dresden, Germany

2006

Using CFD to simulate turbulent mixing in nuclear reactor pressure vessels
Rohde, U.; Höhne, T.; Kliem, S.
  • ANSYS Solutions 7(2006)2, 27-28

Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermal-hydraulic 3D kinetics code
Bousbia Salah, A.; Kliem, S.; Rohde, U.; D’Auria, F.; Petruzzi, A.

Analyses of the V1000CT-1 benchmark with the DYN3D/ATHLET and DYN3D/RELAP coupled code systems including a coolant mixing model validated against CFD calculations
Kliem, S.; Kozmenkov, Y.; Höhne, T.; Rohde, U.

Modeling of a buoyancy-driven flow experiment at the ROCOM test facility using the CFD-codes CFX-5 and TRIO_U
Höhne, T.; Kliem, S.; Bieder, U.

2005

Validation of coupled codes using VVER plant measurements
Vanttola, T.; Hämäläinen, A.; Kliem, S.; Kozmenkov, Y.; Weiß, F.-P.; Kereszturi, A.; Hadek, J.; Strmensky, C.; Stefanova, S.; Kuchin, A.
  • Nuclear Engineering and Design 235(2005), 507-519 (2005)

Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients
Langenbuch, S.; Krzykacz-Hausmann, B.; Schmidt, K.-D.; Hegyi, G.; Kereszturi, A.; Kliem, S.; Hadek, J.; Danilin, S.; Nikonov, S.; Kuchin, A.
  • Nuclear Engineering and Design 235(2005), 521-540

Fluid mixing and flow distribution in the reactor circuit - Part 1: Measurement data base
Rohde, U.; Kliem, S.; Höhne, T.; Karlsson, R.; Hemström, B.; Lillington, J.; Toppila, T.; Elter, J.; Bezrukov, Y.
  • Nuclear Engineering and Design, 235(2005), 421-443

2004

Core response of a PWR to a slug of under-borated water
Kliem, S.; Rohde, U.; Weiß, F.-P.

Analysis of the Boiling Water Reactor Turbine Trip Benchmark with the Codes DYN3D and ATHLET/DYN3D
Grundmann, U.; Kliem, S.; Rohde, U.
  • Nuclear Science and Engineering 148(2004), 226-234

2003

Experimental and Numerical Investigation of Boron Dilution Transients in Pressurized Water Reactors
Hertlein, R.; Umminger, K.; Kliem, S.; Prasser, H.-M.; Höhne, T.; Weiß, F.-P.
  • Nuclear Technology, vol. 141,January 2003, pp. 88-107

Coolant mixing in a PWR - deboration transients, steam line breaks and emergency core cooling injection - experiments and analyses
Prasser, H.-M.; Grunwald, G.; Höhne, T.; Kliem, S.; Rohde, U.; Weiss, F.-P.
  • Lecture (Conference)
    International Congress on Advanced Nuclear Power Plants (ICAPP), June 9-13, 2002 - Hollywood Florida, USA, Proc. CD-ROM, paper #1214.
  • Nuclear Technology 143 (2003) 37-56
  • Contribution to proceedings
    International Congress on Advanced Nuclear Power Plants (ICAPP), June 9-13, 2002 - Hollywood Florida, USA, Proc. CD-ROM, paper #1214.

Analyses of the OECD Main Steam Line Break Benchmark with the Codes DYN3D and ATHLET
Grundmann, U.; Kliem, S.
  • Nuclear Technology 142(2003) 146-153

2002

Validation of coupled neutron kinetic / thermal-hydraulic codes Part 2: Analysis of a VVER-440 transient (Loviisa-1)
Hämäläinen, A.; Kyrki-Rajamäki, R.; Mittag, S.; Kliem, S.; Weiss, F.-P.; Langenbuch, S.; Danilin, S.; Hadek, J.; Hegyi, G.
  • Annals of Nuclear Energy 29 (2002) 255-269

2001

Validation of coupled neutron kinetic / thermal-hydraulic codes Part 1: Analysis of a VVER-1000 transient (Balakovo-4)
Mittag, S.; Kliem, S.; Weiß, F.-P.; Kyrki-Rajamäki, R.; Hämäläinen, A.; Langenbuch, S.; Danilin, S.; Hadek, J.; Hegyi, G.; Kuchin, A.; Panayotov, D.
  • Annals of Nuclear Energy 28/9 (2001) 857-873