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Dr. Sören Kliem

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Veröffentlichungen zum Programm DYN3D

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.

Analysis of loss of flow without scram test in the FFTF reactor – Part II: System thermal hydraulics with point neutron kinetics

Ponomarev, A.; Nikitin, E.; Fridman, E.

Verknüpfte Publikationen

Analysis of loss of flow without scram test in the FFTF reactor – Part I: preparation of neutronics data

Nikitin, E.; Fridman, E.; Ponomarev, A.

Verknüpfte Publikationen

2023

Coupled 3D neutronics/thermal-hydraulics analysis of Superphénix start-up tests with DYN3D/ATHLET code system

Ponomarev, A.; Nikitin, E.; Fridman, E.

Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European SFR Core Power Distribution

Lindley, B.; Álvarez Velarde, F.; Baker, U.; Bodi, J.; Cosgrove, P.; Charles, A.; Fiorina, C.; Fridman, E.; Krepel, J.; Lavarenne, J.; Mikityuk, K.; Nikitin, E.; Ponomarev, A.; Radman, S.; Shwageraus, E.; Tollit, B.

Verknüpfte Publikationen

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.

Verknüpfte Publikationen

2022

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.

2021

DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part I)

Davies, S.; Litskevich, D.; Rohde, U.; Detkina, A.; Merk, B.; Bryce, P.; Levers, A.; Ravindra, V.

Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part II: methodology application

Di Nora, V. A.; Fridman, E.; Nikitin, E.; Bilodid, Y.; Mikityuk, K.

Verknüpfte Publikationen

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

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

Verknüpfte Publikationen

Neutron noise patterns from coupled fuel-assembly vibrations

Viebach, M.; Lange, C.; Seidl, M.; Bilodid, Y.; Hurtado, A.

CTF and FLOCAL Thermal Hydraulics Validations and Verifications within a Multiscale and Multiphysics Software Development

Davies, S.; Rohde, U.; Litskevich, D.; Merk, B.; Bryce, P.; Levers, A.; Detkina, A.; Atkinson, S.; Ravindra, V.

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.

Verknüpfte Publikationen

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

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

Verknüpfte Publikationen

  • ASTRID-DYN3D
    ROBIS: 32353 HZDR-primary research data are used by this (Id 29937) publication
  • Beitrag zu Proceedings
    Physics of Reactors PHYSOR 2020, 29.03.-02.04.2020, Cambridge, United Kingdom, 978-1-5272-6447-2
  • Open Access Logo European Physical Journal Web of Conferences 247(2021), 02028
    DOI: 10.1051/epjconf/202124702028

2020

Detailed Simulation of the Nominal Flow and Temperature Conditions in a Pre-Konvoi PWR Using Coupled CFD and Neutron Kinetics

Höhne, T.; Kliem, S.

  • Beitrag zu Proceedings
    CFD4NRS-8 : Computational Fluid Dynamics for Nuclear Reactor Safety - OECD/NEA Workshop, 25.-27.11.2020, Palaiseau, Frankreich
  • Vortrag (Konferenzbeitrag)
    CFD4NRS-8 : Computational Fluid Dynamics for Nuclear Reactor Safety - OECD/NEA Workshop, 25.-27.11.2020, Palaiseau, Frankreich
  • Open Access Logo Fluids 5(2020)3, 161
    Online First (2020) DOI: 10.3390/fluids5030161

2019

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

Nikitin, E.; Fridman, E.

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.

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.

The HEXNEM3 nodal flux expansion method for the hexagonal geometry in the code DYN3D

Bilodid, Y.; Grundmann, U.; Kliem, S.

Validation of the DYN3D-Serpent code system for SFR cores using selected BFS experiments. Part II: DYN3D calculations.

Rachamin, R.; Kliem, S.

Neutron Noise Observations in German KWU Built PWR and Analyses with the Reactor Dynamics Code DYN3D

Rohde, U.; Seidl, M.; Kliem, S.; Bilodid, Y.

2017

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.

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.

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

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.

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.

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

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

Coupling of the 3D neutron kinetic core model DYN3D with the CFD software ANSYS CFX

Grahn, A.; Kliem, S.; Rohde, U.

  • Beitrag zu Proceedings
    ASME 2014 22nd International Conference on Nuclear Engineering (ICONE22), 07.-11.07.2014, Prag, Tschechische Republik
    Proceedings of ICONE22
  • Vortrag (Konferenzbeitrag)
    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

Development of a general coupling interface for the fuel performance code TRANSURANUS tested with the reactor dynamics code DYN3D

Holt, L.; Rohde, U.; Seidl, M.; Schubert, A.; van Uffelen, P.

2014

Implementation of a fast running full core pin power reconstruction method in DYN3D

Gomez, A.; Sanchez Espinosa, V. H.; Kliem, S.; Gommlich, A.

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.

2013

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

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

The reactor dynamics code DYN3D and its trigonal-geometry nodal diffusion model

Duerigen, S.; Rohde, U.; Bilodid, Y.; Mittag, S.

  • Kerntechnik 78(2013)4, 310-318

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.

Overview of major HZDR developments for fast reactor analysis

Merk, B.; Glivici-Cotruţă, V.; Duerigen, S.; Rohde, U.; Kliem, S.

2012

Simulation of RUTA-70 reactor with CERMET fuel using DYN3D/ATHLET and DYN3D/RELAP5 coupled codes

Kozmenkov, Y.; Rohde, U.; Baranaev, Y.; Glebov, A.

  • Kerntechnik 77(2012)4, 249-257

Assessment of spectral history influence on PWR and WWER core

Bilodid, Y.; Ovdiienko, I.; Mittag, S.; Kuchin, A.; Khalimonchuk, V.; Leremenko, M.

  • Kerntechnik 77(2012)4, 278-285
    ISSN: 0932-3902

The simplified P3 approach on a trigonal geometry of the nodal reactor code DYN3D

Duerigen, S.; Fridman, E.

  • Kerntechnik 4(2012), 226-229

Studies on Boiling Water Reactor design with reduced moderation and analysis of reactivity accidents using the code DYN3D-MG

Rohde, U.; Pivovarov, V. A.; Matveev, Y. A.

  • Kerntechnik 77(2012)4, 240-248
    ISSN: 0932-3902

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.

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

Super-homogenisation factors in pinwise calculations by the reactor dynamics code DYN3D

Grundmann, U.; Mittag, S.

  • Annals of Nuclear Energy 38(2011), 2111-2119

On the use of the Serpent Monte Carlo code for few-group cross section generation

Fridman, E.; Leppänen, J.

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.

  • Eingeladener Vortrag (Konferenzbeitrag)
    Fachtag der KTG: "Aktuelle Themen der Reaktorsicherheitsforschung in Deutschland", 07.-08.10.2010, Dresden, Deutschland
  • Beitrag zu 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

2010

Use of the local Pu-239 concentration as an indicator of burnup spectral history in DYN3D

Bilodid, I.; Mittag, S.

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.

  • Beitrag zu Proceedings
    Jahrestagung Kerntechnik 2008, 27.-29.05.2008, Hamburg, Germany
    Tagungsband der Jahrestagung Kerntechnik 2008, CDROM, Berlin: INFORUM GmbH
  • Eingeladener Vortrag (Konferenzbeitrag)
    Jahrestagung Kerntechnik 2008, 27.-29.05.2008, Hamburg, Germany
  • atw - International Journal for Nuclear Power 54(2009)2, 100-110
    ISSN: 1431-5254

2008

Dynamics of Molten Salt Reactors

Krepel, J.; Grundmann, U.; Rohde, U.; Weiss, F.-P.

  • Nuclear Technology 164(2008), 34-44

Development and verification of a nodal approach for solving the multigroup SP3 equations

Beckert, C.; Grundmann, U.

  • Annals of Nuclear Energy 35(2008)1, 75-86

2007

DYN3D - Advanced Reactor Simulations in 3D

Rohde, U.; Grundmann, U.; Kliem, S.

  • Nuclear Energy Review 2(2007), 28-30
    ISSN: 1753-3910

Multigroup Diffusion and SP3 Solutions for a PWR MOX/UO2 Benchmark with the Code DYN3D

Beckert, C.; Grundmann, U.; Mittag, S.

  • Transactions of the American Nuclear Society and the European Nuclear Society 97(2007)
  • Vortrag (Konferenzbeitrag)
    2007 ANS/ENS International Meeting, 11.-15.11.2007, Washington D.C., United States

DYN3D-MSR spatial dynamics code for Molten Salt Reactors

Krepel, J.; Rohde, U.; Grundmann, U.; Weiß, F.-P.

  • Annals of Nuclear Energy 34(2007), 449-462

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.

2006

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.

2005

DYN1D-MSR dynamics code for molten salt reactors

Krepel, J.; Rohde, U.; Grundmann, U.; Weiss, F.-P.

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)

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

Discontinuity factors for non-multiplying material in two-dimensional hexagonal reactor geometry

Mittag, S.; Petkov, P.; Grundmann, U.

  • Annals of Nuclear Energy 30/13 (2003) pp. 1347-1364

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

2001

The Modeling of Fuel Rod Behaviour under RIA Conditions in the Code DYN3D

Rohde, U.

  • Annals of Nuclear Energy 28 (2001), Vol. 13, pp. 1343-1363

2000

Experimental Investigations on the Four-Loop Test Facility ROCOM

Höhne, T.; Grunwald, G.; Prasser, H.-M.

  • Kerntechnik 65/5-6, S. 212-215

1999

Comparative Study of a Boron Dilution Scenario in VVER Reactors

Ivanov, K. N.; Grundmann, U.; Mittag, S.; Rohde, U.

  • Annals of Nuclear Energy 26 (1999) 1331-1339

A Two-Dimensional Intranodal Flux Expansion Method for Hexagonal Geometry

Grundmann, U.; Hollstein, F.

  • Nuclear Science and Engineering 133 (1999) 201-212

1997

Analysis of a boron dilution accident for WWER-440 combining the use of the codes DYN3D and SiTAP

Rohde, U.; Elkin, I.; Kalinenko, V.

  • Nuclear Engineering and Design 170 (1997), pp. 95 - 99

Neutron Flux Reconstruction ina Hexagonal Cassete - Theory and Implementation into the Code DYN3D/H1.1

Hadek, J.; Grundmann, U.

  • Nucleon No. 3, (1997), pp. 8 - 14