Contact

Dr. Sören Kliem

Head
Reactor Safety
s.kliemAthzdr.de
Phone: +49 351 260 2318

Publications concerning the DYN3D code

2019

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

Nikitin, E.; Fridman, E.ORC

A realistic approach for the assessment of the consequences of heterogeneous boron dilution events in pressurized water reactors

Kliem, S.ORC; Grahn, A.; Bilodid, Y.ORC; 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.ORC; Kotlyar, D.

2018

Explicit decay heat calculation in the nodal diffusion code DYN3D

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

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.ORC; 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.

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

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

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.
  • 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

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.

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.

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: 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.

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

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

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.
  • 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

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.
  • 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

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

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)
  • Lecture (Conference)
    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


Contact

Dr. Sören Kliem

Head
Reactor Safety
s.kliemAthzdr.de
Phone: +49 351 260 2318