Personal web page of Sören Kliem
Scientific career
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Since 2010:Department head "Reactor Safety" at the Helmholtz-Zentrum Dresden- Rossendorf, Institute of Resource Ecology
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2010:PhD at Technical University Dresden, Faculty of Machinery Building
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1994-2010:Scientific co-worker at the Forschungszentrum Rossendorf, Institute of Safety Research
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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
- 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
- Horizon 2020 R2CA: Reduction of radiological consequences of design basis and design extension accidents, 2019 - 2023
- Horizon 2020 McSAFER: High-Performance Advanced Methods and Experimental Investigations for the Safety Evaluation of Generic Small Modular Reactors, 2020 - 2023
Publications
2024
NuScale-like SMR Model Development and Applied Safety Analyses with the Code Chain Serpent-DYN3D-ATHLET
Diaz Pescador, E.; Bilodid, Y.; Jobst, M.; Kliem, S.
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Nuclear Engineering and Design 418(2024), 112909
DOI: 10.1016/j.nucengdes.2024.112909
Cited 1 times in Scopus
Numerical investigation on steam condensation and heat transfer in an emergency condenser tube with the thermo-hydraulic system code ATHLET: Post-test simulation of a series of COSMEA tests
Jobst, M.; Schäfer, F.; Kliem, S.
Involved research facilities
- TOPFLOW Facility
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Nuclear Engineering and Design 421(2024), 113059
DOI: 10.1016/j.nucengdes.2024.113059
2023
Extension of the X2 VVER-1000 benchmark by a control rod cluster ejection exercise
Bilodid, Y.; Fischer, M.; Zilly, M.; Aures, A.; Henry, R.; Kilger, R.; Kliem, S.
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Annals of Nuclear Energy 192(2023), 110007
DOI: 10.1016/j.anucene.2023.110007
Cited 2 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.
Related publications
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Phenix EOL natural convection test: Serpent/DYN3D/ATHLET I/O data
ROBIS: 35779 HZDR-primary research data are used by this (Id 35760) publication -
Phenix EOL natural convection test: Serpent/DYN3D/ATHLET I/O data
RODARE: 2007 HZDR-primary research data are used by this (Id 35760) publication
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Annals of Nuclear Energy 182(2023), 109619
Online First (2022) DOI: 10.1016/j.anucene.2022.109619
Cited 8 times in Scopus
Numerical Analysis Related to the ROCOM Pressurized Thermal Shock Benchmark
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Fluids 8(2023)1, 4
Online First (2022) DOI: 10.3390/fluids8010004
Cited 3 times in Scopus
2022
On the validation of ATHLET 3-D features for the simulation of multidimensional flows in horizontal geometries under single-phase subcooled conditions
Diaz Pescador, E.; Schäfer, F.; Kliem, S.
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Nuclear Engineering and Technology 54(2022), 3567-3579
DOI: 10.1016/j.net.2022.04.017
Cited 1 times in Scopus
Verification of the code DYN3D for calculations of neutron flux fluctuations
Viebach, M.; Lange, C.; Kliem, S.; Demaziere, C.; Rohde, U.; Hennig, D.; Hurtado, A.
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Annals of Nuclear Energy 166(2022), 108735
Online First (2021) DOI: 10.1016/j.anucene.2021.108735
Cited 3 times in Scopus
2021
The H2020 McSAFER project: Main goals, technical work program, and status
Sanchez-Espinoza, V. H.; Gabriel, S.; Suikkanen, H.; Telkkä, J.; Valtavirta, V.; Bencik, M.; Kliem, S.; Queral, C.; Farda, A.; Abéeguilée, F.; Smith, P.; van Uffelen, P.; Ammirabile, L.; Seidl, M.; Schneidesch, C.; Grishchenko, D.; Lestani, H.
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Energies 14(2021), 6348
DOI: 10.3390/en14196348
Cited 22 times in Scopus
SERPENT2-SUBCHANFLOW-TRANSURANUS pin-by-pin depletion calculations for a PWR fuel assembly
Garcia, M.; Tuominen, R.; Gommlich, A.; Ferraro, D.; Valtavirta, V.; Imke, U.; van Uffelen, P.; Mercatali, L.; Sanchez-Espinoza, V.; Leppänen, J.; Kliem, S.
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European Physical Journal Web of Conferences 247(2021), 06016
DOI: 10.1051/epjconf/202124706016
Cited 3 times in Scopus
Modelling of complex boron dilution transients in PWRs—Validation of CFD simulation with ANSYS CFX against the ROCOM E2.3 experiment
Grahn, A.; Diaz Pescador, E.; Kliem, S.; Schäfer, F.; Höhne, T.
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Nuclear Engineering and Design 372(2021), 110938
DOI: 10.1016/j.nucengdes.2020.110938
Cited 5 times in Scopus
Modelling of multidimensional effects in thermal-hydraulic system codes under asymmetric flow conditions – Simulation of ROCOM Tests 1.1 and 2.1 with ATHLET 3D-Module
Diaz Pescador, E.; Schäfer, F.; Kliem, S.
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Nuclear Engineering and Technology 53(2021)10, 3182-3195
DOI: 10.1016/j.net.2021.04.015
Cited 6 times in Scopus
2020
Detailed Simulation of the Nominal Flow and Temperature Conditions in a Pre-Konvoi PWR Using Coupled CFD and Neutron Kinetics
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Contribution to proceedings
CFD4NRS-8 : Computational Fluid Dynamics for Nuclear Reactor Safety - OECD/NEA Workshop, 25.-27.11.2020, Palaiseau, Frankreich -
Lecture (Conference)
CFD4NRS-8 : Computational Fluid Dynamics for Nuclear Reactor Safety - OECD/NEA Workshop, 25.-27.11.2020, Palaiseau, Frankreich -
Fluids 5(2020)3, 161
DOI: 10.3390/fluids5030161
Cited 1 times in Scopus
Advanced modelling of complex boron dilution transients in PWRs – Validation of ATHLET 3D-Module against the experiment ROCOM E2.3
Diaz Pescador, E.; Grahn, A.; Kliem, S.; Schäfer, F.; Höhne, T.
Related publications
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Experimental data of the ROCOME2.3 experiment
ROBIS: 31562 HZDR-primary research data are used by this (Id 30098) publication
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Nuclear Engineering and Design 367(2020), 110776
DOI: 10.1016/j.nucengdes.2020.110776
Cited 9 times in Scopus
A SERPENT2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors
Garcia, M.; Tuominen, R.; Gommlich, A.; Ferraro, D.; Valtavirta, V.; Imke, U.; van Uffelen, P.; Mercatali, L.; Sanchez, V.; Leppänen, J.; Kliem, S.
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Annals of Nuclear Energy 139(2020), 107213
DOI: 10.1016/j.anucene.2019.107213
Cited 23 times in Scopus
The efficiency of sequential accident management measures for a German PWR under prolonged SBO conditions
Kozmenkov, Y.; Jobst, M.; Kliem, S.; Kosowski, K.; Schäfer, F.; Wilhelm, P.
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Nuclear Engineering and Design 363(2020), 110663
DOI: 10.1016/j.nucengdes.2020.110663
Cited 7 times in Scopus
2019
Thermal-hydraulic insights during a main steam line break in a generic PWR KONVOI reactor with ATHLET 3.1A
Diaz Pescador, E.; Schäfer, F.; Kliem, S.
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Kerntechnik 84(2019)5, 367-374
DOI: 10.3139/124.190008
Cited 3 times in Scopus
A realistic approach for the assessment of the consequences of heterogeneous boron dilution events in pressurized water reactors
Kliem, S.; Grahn, A.; Bilodid, Y.; Höhne, T.
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Nuclear Engineering and Design 349(2019), 150-161
DOI: 10.1016/j.nucengdes.2019.04.038
Cited 7 times in Scopus
2018
Severe Accident Management Measures for a Generic German PWR. Part II: Small-break loss-of-coolant accident
Jobst, M.; Wilhelm, P.; Kozmenkov, Y.; Kliem, S.
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Annals of Nuclear Energy 122(2018), 280-296
DOI: 10.1016/j.anucene.2018.08.017
Cited 11 times in Scopus
Severe accident management measures for a generic German PWR. Part I: Station blackout
Wilhelm, P.; Jobst, M.; Kozmenkov, Y.; Schäfer, F.; Kliem, S.
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Annals of Nuclear Energy 122(2018), 217-228
DOI: 10.1016/j.anucene.2018.08.016
Cited 15 times in Scopus
The HEXNEM3 nodal flux expansion method for the hexagonal geometry in the code DYN3D
Bilodid, Y.; Grundmann, U.; Kliem, S.
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Annals of Nuclear Energy 116(2018), 187-194
DOI: 10.1016/j.anucene.2018.02.037
Cited 12 times in Scopus
Validation of the DYN3D-Serpent code system for SFR cores using selected BFS experiments. Part II: DYN3D calculations.
Rachamin, R.; Kliem, S.
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Annals of Nuclear Energy 114(2018), 181-190
DOI: 10.1016/j.anucene.2017.12.036
Cited 2 times in Scopus
IAEA CRP benchmark of ROCOM PTS test case for the use of CFD in reactor design using the CFD-codes ANSYS CFX and TRIOCFD
Höhne, T.; Kliem, S.; Bieder, U.
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Nuclear Engineering and Design 333(2018), 161-180
DOI: 10.1016/j.nucengdes.2018.04.017
Cited 30 times in Scopus
Neutron Noise Observations in German KWU Built PWR and Analyses with the Reactor Dynamics Code DYN3D
Rohde, U.; Seidl, M.; Kliem, S.; Bilodid, Y.
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Annals of Nuclear Energy 112(2018), 715-734
DOI: 10.1016/j.anucene.2017.10.033
Cited 19 times in Scopus
Unsteady single phase natural circulation flow mixing prediction using 3D thermal-hydraulic system and CFD codes
Bousbia Salah, A.; Ceuca, S. C.; Puragliesi, R.; Mukin, R.; Grahn, A.; Kliem, S.; Vlassenbroeck, J.; Austregesilo, H.
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Nuclear Technology 203(2018), 293-314
DOI: 10.1080/00295450.2018.1461517
Cited 11 times in Scopus
2017
Testing the NURESIM platform on a PWR main steam line break benchmark
Kliem, S.; 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.
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Nuclear Engineering and Design 321(2017), 8-25
DOI: 10.1016/j.nucengdes.2017.05.028
Cited 8 times in Scopus
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.
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Nuclear Engineering and Design 315(2017), 117-127
DOI: 10.1016/j.nucengdes.2017.02.002
Cited 15 times in Scopus
Validation of the DYN3D-Serpent code system for SFR cores using selected BFS experiments. Part I: Serpent calculations.
Rachamin, R.; Kliem, S.
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Annals of Nuclear Energy 102(2017), 158-167
DOI: 10.1016/j.anucene.2016.12.023
Cited 9 times in Scopus
Statistical Analysis of the Early Phase of SBO Accident for PWR
Kozmenkov, Y.; Jobst, M.; Kliem, S.; Schaefer, F.; Wilhelm, P.
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Nuclear Engineering and Design 314(2017), 131-141
DOI: 10.1016/j.nucengdes.2017.02.001
Cited 8 times in Scopus
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.
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Progress in Nuclear Energy 89(2016), 170-190
DOI: 10.1016/j.pnucene.2016.02.013
Cited 123 times in Scopus
Hybrid microscopic depletion model in nodal code DYN3D
Bilodid, Y.; Kotlyar, D.; Shwageraus, E.; Fridman, E.; Kliem, S.
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Annals of Nuclear Energy 92(2016), 397-406
DOI: 10.1016/j.anucene.2016.02.012
Cited 12 times in Scopus
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.
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Nuclear Engineering and Design 297(2016), 32-43
DOI: 10.1016/j.nucengdes.2015.11.005
Cited 9 times in Scopus
2015
Validation and verification of the coupled neutron kinetic/thermalhydraulic system code DYN3D/ATHLET
Kozmenkov, Y.; Kliem, S.; Rohde, U.
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Annals of Nuclear Energy 84(2015), 153-165
DOI: 10.1016/j.anucene.2014.12.012
Cited 41 times in Scopus
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.
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Annals of Nuclear Energy 84(2015), 86-97
DOI: 10.1016/j.anucene.2014.11.002
Cited 29 times in Scopus
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.
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Annals of Nuclear Energy 84(2015), 166-177
DOI: 10.1016/j.anucene.2014.12.013
Cited 66 times in Scopus
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.
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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.
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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: 10.1016/j.anucene.2014.12.015
Cited 26 times in Scopus
2014
Implementation of a fast running full core pin power reconstruction method in DYN3D
Gomez, A.; Sanchez Espinosa, V. H.; Kliem, S.; Gommlich, A.
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Nuclear Engineering and Design 274(2014), 44-55
DOI: 10.1016/j.nucengdes.2014.04.028
Cited 14 times in Scopus
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.
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Nuclear Engineering and Design 277(2014), 106-116
DOI: 10.1016/j.nucengdes.2014.06.011
Cited 13 times in Scopus
Coolant mixing experiments in the upper plenum of the ROCOM test facility
Prasser, H.-M.; Kliem, S.
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Nuclear Engineering and Design 276(2014), 30-42
DOI: 10.1016/j.nucengdes.2014.05.016
Cited 20 times in Scopus
Fuel cycle advantages and dynamics features of liquid fueled MSR
Krepel, J.; Hombourger, B.; Fiorina, C.; Mikityuk, K.; Rohde, U.; Kliem, S.; Pautz, A.
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Annals of Nuclear Energy 64(2014), 380-397
DOI: 10.1016/j.anucene.2013.08.007
Cited 53 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.
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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
Cited 5 times in Scopus
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.
Involved research facilities
- TOPFLOW Facility
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Nuclear Engineering and Design 258(2013), 241-248
DOI: 10.1016/j.nucengdes.2013.02.001
Cited 6 times in Scopus
Overview of major HZDR developments for fast reactor analysis
Merk, B.; Glivici-Cotruţă, V.; Duerigen, S.; Rohde, U.; Kliem, S.
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Nuclear Engineering and Design 265(2013), 1194-1204
DOI: 10.1016/j.nucengdes.2013.07.026
Cited 1 times in Scopus
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.
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Kerntechnik 77(2012)4, 212-212
ISSN: 0932-3902
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.
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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
2011
Buoyancy driven mixing studies of natural circulation flows using ROCOM experiments and CFD
Höhne, T.; Kliem, S.; Rohde, U.
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Chemie Ingenieur Technik 83(2011)8, 1282-1289
DOI: 10.1002/cite.201100035
Cited 3 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
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.
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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.
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Nuclear Engineering and Design 241(2011)1, 193-202
DOI: 10.1016/j.nucengdes.2010.10.036
Cited 56 times in Scopus
Burning plutonium and minimizing radioactive waste in existing PWRs
Mittag, S.; Kliem, S.
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Annals of Nuclear Energy 38(2011), 98-102
DOI: 10.1016/j.anucene.2010.08.012
Cited 21 times in Scopus
2010
Bedeutung von Experimenten für die Reaktorsicherheit
Teschendorff, V.; Glaeser, H.; Kliem, S.
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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
ISSN: 1431-5254
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.
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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: 10.1016/j.nucengdes.2009.11.015
Cited 30 times in Scopus
Application of CFD codes in nuclear reactor safety analysis
Rohde, U.; Höhne, T.; Krepper, E.; Kliem, S.
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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 -
Science and Technology of Nuclear Installations 2010(2010), Article ID 198758
DOI: 10.1155/2010/198758
Cited 25 times in Scopus
2009
ATWS analysis for PWR using the coupled code system DYN3D/ATHLET
Kliem, S.; Mittag, S.; Rohde, U.; Weiß, F.-P.
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Annals of Nuclear Energy 36(2009), 1230-1234
DOI: 10.1016/j.anucene.2009.04.001
Cited 13 times in Scopus
Simulation von ATWS-Transienten in Druckwasserreaktoren
Kliem, S.; Mittag, S.; Rohde, U.; Grundmann, U.; Weiß, F.-P.
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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
ISSN: 1431-5254
Experimental and numerical modeling of transition matrix from momentum to buoyancy-driven flow in a pressurized water reactor
Höhne, T.; Kliem, S.; Vaibar, R.
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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: 10.1115/1.2983137
Cited 16 times in Scopus
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.
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Nuclear Engineering and Design 238(2008)7, 1788-1801
DOI: 10.1016/j.nucengdes.2007.10.016
Cited 25 times in Scopus
CFX simulations of ROCOM slug mixing experiments
Moretti, F.; Melideo, D.; DAuria, F.; Höhne, T.; Kliem, S.
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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 -
Journal of Power and Energy Systems 2(2008)2, 720-733
DOI: 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.
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Nuclear Engineering and Design 238(2008), 1987-1995
DOI: 10.1016/j.nucengdes.2007.10.032
Cited 44 times in Scopus
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.
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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: 10.1016/j.nucengdes.2007.02.053
ISSN: 0029-5493
Cited 84 times in Scopus
2007
DYN3D - Advanced Reactor Simulations in 3D
Rohde, U.; Grundmann, U.; Kliem, S.
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Nuclear Energy Review 2(2007), 28-30
ISSN: 1753-3910
Jahrestagung Kerntechnik - Sektionsbericht Sektion: Thermo- und Fluiddynamik
Stieglitz, R.; Kliem, S.
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atw - International Journal for Nuclear Power 52(2007)10, 652-654
ISSN: 1431-5254
Comparative evaluation of coolant mixing experiments at the ROCOM, Vattenfall, and Gidropress test facilities
Kliem, S.; Hemström, B.; Bezrukov, Y.; Höhne, T.; Rohde, U.
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Science and Technology of Nuclear Installations 2007(2007), 25950
DOI: 10.1155/2007/25950
ISSN: 1687-6075 -
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.
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Nuclear 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.
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Nuclear Engineering and Design 237(2007)15-17, 1639-1655
DOI: 10.1016/j.nucengdes.2007.03.015
Cited 108 times in Scopus
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.
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Nuclear Engineering and Design 237(2007)7, 732-748
DOI: 10.1016/j.nucengdes.2006.08.010
ISSN: 0029-5493
Cited 26 times in Scopus
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.
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atw - International Journal for Nuclear Power 3(2007), 168-174
ISSN: 1431-5254
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.
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Nuclear Engineering and Design 237(2007)15-17, 1938-1951
DOI: 10.1016/j.nucengdes.2007.02.021
Cited 33 times in Scopus
Experimente an der Versuchsanlage ROCOM zur Kühlmittelvermischung bei Wiederanlauf der Naturzirkulation
Kliem, S.; Sühnel, T.; Prasser, H.-M.; Weiß, F.-P.
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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
ISSN: 1431-5254 -
Invited lecture (Conferences)
KTG-Fachtag "Aktuelle Themen der Reaktorsicherheitsforschung in Deutschland", 03.-04.04.2006, Dresden, Germany
2006
Simulating 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.; DAuria, F.; Petruzzi, A.
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Nuclear Engineering and Design 236(2006), 1240-1255
DOI: 10.1016/j.nucengdes.2005.11.005
ISSN: 0029-5493
Cited 13 times in Scopus
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.
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Progress in Nuclear Energy 48(2006), 830-848
DOI: 10.1016/j.pnucene.2006.06.008
Cited 26 times in Scopus
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.
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Nuclear Engineering and Design 236(2006)12, 1309-1325
DOI: 10.1016/j.nucengdes.2005.12.005
Cited 79 times in Scopus
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.
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Nuclear Engineering and Design 230(2004), 121-132
DOI: 10.1016/j.nucengdes.2003.11.021
Cited 32 times in Scopus
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.
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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
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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