Dr.-Ing. T. Höhne

Helmholtz-Zentrum Dresden-Rossendorf (HZDR)

Institut für Fluiddynamik

Abteilung CFD

Postfach 51 01 19
D-01314 Dresden
Deutschland

Tel.: +49 351 260 2425
Fax: +49 351 260 2383

email: t.hoehne@hzdr.de

 

Publikationen in ref. Zeitschriften

Hänsch, S.; Lucas, D.; Höhne, T.; Krepper, E.
Application of a new concept for multi-scale interfacial structures to the dam-break case with an obstacle
Nuclear Engineering and Design (2013)

Mehlhoop, J.-P.; Höhne, T.
Validation of closure models for interfacial drag and turbulence in numerical simulations of horizontal stratified gas-liquid flows
International Journal of Multiphase Flow (2013)

Höhne, T.
Thermal-Hydraulic Investigations for Safety Related Tasks
atw - International Journal for Nuclear Power (2013)

Höhne, T.
Scale Resolved Simulations of the OECD/NEA−Vattenfall T-Junction Benchmark using LES methods
Nuclear Engineering and Design (2013)

Stieglitz, R.; Mull, T.; Höhne, T.; Rieger, U.; Buettner, K.
Section Reports: 2012 Annual Meeting on Nuclear Technology - Part 5
atw - International Journal for Nuclear Power 58(2013)1, 43-44

Höhne, T.
Development and validation of a morphology detection algorithm (AIAD) for horizontal two phase flows
Petrobras Technical Bulletin (2013)

Lucas, D.; Coste, P.; Höhne, T.; Lakehal, D.; Bartosiewicz, Y.; Bestion, D.; Scheuerer, M.; Galassi, M. C.
CFD modeling of free surface flow with and without condensation
Multiphase Science and Technology 23(2011), 253-342

Hänsch, S.; Lucas, D.; Krepper, E.; Höhne, T.
A multi-field two-fluid concept for transitions between different scales of interfacial structures
International Journal of Multiphase Flow 47(2012), 171-182

Höhne, T.; Grahn, A.; Kliem, S.; Rohde, U.; Weiss, F.-P.
Numerical simulation of the insulation material transport in a PWR core under loss of coolant conditions
Nuclear Engineering and Design 258(2013), 241-248

Höhne, T.; Darlianto, D.; Lucas, D.
Numerical simulations of CCFL experiments using a morphology detection algorithm
The Journal of Computational Multiphase Flows 4(2012)3, 271-286

Montoya, G.; Deendarlianto; Lucas, D.; Höhne, T.; Vallee, C.
Image-Processing-Based Study of the Interfacial Behavior of the Countercurrent Gas-Liquid Two-Phase Flow in a Hot Leg of a PWR
Science and Technology of Nuclear Installations 2012(2012), ID 209542

Prayitno, S.; Santoso, R.; Darlianto, D.; Höhne, T.; Lucas, D.
Counter-current Flow Limitation of Gas-Liquid Two phase Flow in Nearly Horizontal Pipe
Science and Technology of Nuclear Installations (2012), 513809

Höhne, T.; Kliem, S.; Rohde, U.
Buoyancy driven mixing studies of natural circulation flows using ROCOM experiments and CFD
Chemie Ingenieur Technik 83(2011)8, 1282-1289

Höhne, T.; Schaffrath, A.
Fachsitzung: „CFD-Methoden für sicherheitsrelevante Fragestellungen“
atw - International Journal for Nuclear Power 56(2011)7, 419-423

Deendarlianto; Höhne, T.; Murase, M.
Countercurrent flow limitations in a pressurized water reactor
Science and Technology of Nuclear Installations (2012), 608678

Deendarlianto,-; Höhne, T.; Apanasevich, P.; Lucas, D.; Vallée, C.; Beyer, M.
Application of a new drag coefficient model at CFD-simulations on free surface flows relevant for the nuclear reactor safety analysis
Annals of Nuclear Energy 39(2012), 70-82

Deendarlianto,-; Höhne, T.; Lucas, D.; Vallée, C.; Montoya, G.
CFD studies on the phenomena around counter-current flow limitations of gas/liquid two-phase flow in a model of a PWR hot leg
Nuclear Engineering and Design 241(2011), 5138-5148

Deendarlianto,-; Höhne, T.; Lucas, D.; Vierow, K.
Gas-liquid countercurrent two-phase flow in a PWR hot leg: a comprehensive research review
Nuclear Engineering and Design 243(2012), 214-233

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

Höhne, T.; Deen, D.; Lucas, D.
Numerical simulations of counter-current two-phase flow experiments in a PWR hot leg model using an interfacial area density model
International Journal of Heat and Fluid Flow 32(2011), 1047-1056

Loginov, M. S.; Komen, E.; Höhne, T.
Application of Large-Eddy Simulation to Pressurized Thermal Shock: assessment of the accuracy
Nuclear Engineering and Design 240(2011), 2034-2045

Moretti, F.; Melideo, D.; Del Nevo, A.; D’Auria, F.; Höhne, T.; Lisenkov, E.; Bucalossi, A.; Gallori, D.
Experimental investigation of in-vessel mixing phenomena in a VVER-1000 scaled test facility during unsteady asymmetric transients
Nuclear Engineering and Design 241(2011)8, 3068-3075

Höhne, T.; Vallée, C.
Experiments and numerical simulations of horizontal two phase flow regimes using an interfacial area density model
The Journal of Computational Multiphase Flows 2(2010)3, 131-143

Höhne, T.
Numerische Strömungsberechnung/Computational Fluid Dynamics
atw - International Journal for Nuclear Power (2010)10, 648-655

Höhne, T.
Anwendung von CFD-Methoden für den Kern sowie den Primärkreislauf von LWR
atw - International Journal for Nuclear Power 8/9(2009), 546-548

Moncalvo, D.; Friedel, L.; Jörgensen, B.; Höhne, T.
Nachrechnung der Leistungsparameter eines Sicherheitsventils mit ANSYS CFX
Forschung im Ingenieurwesen - Engineering Research 73(2009)2, 99-103

Höhne, T.; Vallee, C.
Modelling of stratified two phase flows using an interfacial area density model
WIT Transactions on Engineering Sciences Volume 63(2009), 123-135

Da Silva, M. J.; Thiele, S.; Höhne, T.; Vaibar, R.; Hampel, U.
Experimental studies and CFD calculations for buoyancy driven mixing phenomena
Nuclear Engineering and Design 240(2010)9, 2185-2193

Moncalvo, L.; Friedel, B.; Jörgensen, T.; Höhne, T.
Sizing of safety valves using ANSYS CFX-Flo
Chemical Engineering & Technology 32(2009)2, 1-6

Höhne, T.
CFD-simulation of the VVER thermal hydraulic benchmark V1000CT–2 using ANSYS CFX
Science and Technology of Nuclear Installations 2009(2009), Article ID 835162

Höhne, T.; Moncalvo, D.; Friedel, L.; Jörgensen, B.
Nachrechnung eines Vollhub-Feder-Sicherheitsventils mit ANSYS CFX
Forschung im Ingenieurwesen - Engineering Research 73(2009)2, 99-103

Moretti, F.; Melideo, D.; Del Nevo, A.; D’Auria, F.; Höhne, T.; Lisenkov, E.
CFD validation against slug mixing experiment
Science and Technology of Nuclear Installations (2009), Article ID 436218

Kliem, S.; Höhne, T.; Rohde, U.; Weiß, F.-P.
Experiments on slug mixing under natural circulation conditions at the ROCOM test facility using high resolution measurement technique and numerical modeling
Nuclear Engineering and Design 240(2010)9, 2271-2280

Rohde, U.; Höhne, T.; Krepper, E.; Kliem, S.
Application of CFD codes in nuclear reactor safety analysis
Science and Technology of Nuclear Installations 2010(2010), Article ID 198758

Bartosiewicz, Y.; Seynhaeve, J.-M.; Vallee, C.; Höhne, T.; Laviéville, J.
Modeling free surface flows relevant to a PTS scenario: comparison between experimental data and three RANS based CFD-codes - Comments on the CFD-experiment integration and best practice guideline
Nuclear Engineering and Design 240(2010), 2375-2381

Höhne, T.; Kliem, S.; Vaibar, R.
Experimental and numerical modeling of transition matrix from momentum to buoyancy-driven flow in a pressurized water reactor
Journal of Engineering for Gas Turbines and Power - Transactions of the ASME 131(2009)1, 012906

Kliem, S.; Hemström, B.; Bezrukov, Y.; Höhne, T.; Rohde, U.
Comparative evaluation of coolant mixing experiments at the ROCOM, Vattenfall, and Gidropress test facilities
Science and Technology of Nuclear Installations 2007(2007), 25950

Höhne, T.
Numerical simulation of coolant mixing in a pressurized water reactor with different CFD methods based on complex meshes
International Journal of Nuclear Energy Science and Technology 3(2007)4, 399-412

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

Moretti, F.; Melideo, D.; D’Auria, F.; Höhne, T.; Kliem, S.
CFX simulations of ROCOM slug mixing experiments
Journal of Power and Energy Systems 2(2008)2, 720-733

Höhne, T.; Kliem, S.; Rohde, U.; Weiss, F.-P.
Boron Dilution Transients during natural circulation flow in PWR – experiments and CFD simulations
Nuclear Engineering and Design 238(2008), 1987-1995

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.
Fluid mixing and flow distribution ín a primary circuit of a nuclear pressurized water reactor – Validation of CFD codes
Nuclear Engineering and Design 237(2007)15-17, 1639-1655

Cartland Glover, G. M.; Höhne, T.; Kliem, S.; Rohde, U.; Weiss, F.-P.; Prasser, H.-M.
Hydrodynamic phenomena in the downcomer during flow rate transients in the primary circuit of a PWR
Nuclear Engineering and Design 237(2007)7, 732-748

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

Zaruba, A.; Lucas, D.; Prasser, H.-M.; Höhne, T.
Bubble-wall interactions in a vertical gas-liquid flow: bouncing, sliding and bubble deformations
Chemical Engineering Science 62(2007), 1591-1605

Kliem, S.; Sühnel, T.; Rohde, U.; Höhne, T.; Prasser, H.-M.; Weiß, F.-P.
Experiments at the mixing test facility ROCOM for benchmarking of CFD-codes
Nuclear Engineering and Design 238(2008), 566-576

Vallee, C.; Höhne, T.; Prasser, H.-M.; Sühnel, T.
Experimental investigation and CFD simulation of horizontal stratified two-phase flow phenomena
Nuclear Engineering and Design 238(2008), 637-646

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

Vallee, C.; Höhne, T.; Prasser, H.-M.; Sühnel, T.
Experimental investigation and CFD simulation of horizontal air/water slug flow
Kerntechnik 71(2006)3, 95-103

Kliem, S.; Kozmenkov, Y.; Höhne, T.; Rohde, U.
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
Progress in Nuclear Energy 48(2006), 830-848

Höhne, T.; Kliem, S.; Bieder, U.
Modeling of a buoyancy-driven flow experiment at the ROCOM test facility using the CFD-codes CFX-5 and TRIO_U
Nuclear Engineering and Design 236(2006)12, 1309-1325

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

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

Prasser, H.-M.; Grunwald, G.; Höhne, T.; Kliem, S.; Rohde, U.; Weiss, F.-P.
Coolant mixing in a PWR - deboration transients, steam line breaks and emergency core cooling injection - experiments and analyses
Nuclear Technology 143 (2003) 37-56

Höhne, T.
Untersuchung der Kühlmittelvermischung in Druckwasserreaktoren
atw 12, S. 774-775

Höhne, T.; Grunwald, G.; Prasser, H.-M.
Experimental Investigations on the Four-Loop Test Facility ROCOM
Kerntechnik 65/5-6, S. 212-215

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