Dr. T. Höhne

Helmholtz-Zentrum Dresden-Rossendorf (HZDR)
Institute of Fluid Dynamics

CFD Department

Bautzner Landstraße 400 | D-01328 Dresden,
Germany

tel.: +49 351 260 2425

fax: +49 351 260 2383

email: t.hoehne@hzdr.de

Selected Publications

  • Höhne, T.; Porombka, P.; Moya Saez, S.
    Validation of AIAD sub-models for advanced numerical modelling of horizontal two-phase flows
    Fluids 5(2020)3, 102 (10.3390/fluids5030102)
  • Höhne, T.; Kliem, S.
    Detailed Simulation of the Nominal Flow and Temperature Conditions in a Pre-Konvoi PWR Using Coupled CFD and Neutron Kinetics
    Contribution to proceedings:
    CFD4NRS-8 : Computational Fluid Dynamics for Nuclear Reactor Safety - OECD/NEA Workshop, 25.-27.11.2020, Palaiseau, Frankreich
  • Höhne, T.; Kliem, S.
    Detailed Simulation of the Nominal Flow and Temperature Conditions in a Pre-Konvoi PWR Using Coupled CFD and Neutron Kinetics
    Lecture (Conference):
    CFD4NRS-8 : Computational Fluid Dynamics for Nuclear Reactor Safety - OECD/NEA Workshop, 25.-27.11.2020, Palaiseau, Frankreich
  • Höhne, T.; Kliem, S.
    Detailed Simulation of the Nominal Flow and Temperature Conditions in a Pre-Konvoi PWR Using Coupled CFD and Neutron Kinetics
    Fluids 5(2020)3, 161 (10.3390/fluids5030161)
  • Höhne, T.; Mamedov, T.
    CFD simulation of aeration and mixing processes in a full-scale oxidation ditch
    Energies 13(2020)7, 1633 (10.3390/en13071633)
  • Höhne, T.
    Simulation of coolant mixing in a BWR spent fuel storage pool and flood chamber
    Nuclear Engineering and Design 359(2020), 110468 (10.1016/j.nucengdes.2019.110468)
  • Diaz Pescador, E.; Grahn, A.; Kliem, S. et al.
    Advanced modelling of complex boron dilution transients in PWRs – Validation of ATHLET 3D-Module against the experiment ROCOM E2.3
    Nuclear Engineering and Design 367(2020), 110776 (10.1016/j.nucengdes.2020.110776)
  • Grahn, A.; Diaz Pescador, E.; Kliem, S. et al.
    Modelling of complex boron dilution transients in PWRs—Validation of CFD simulation with ANSYS CFX against the ROCOM E2.3 experiment
    Nuclear Engineering and Design 372(2021), 110938 (10.1016/j.nucengdes.2020.110938)
  • Boumaza, M.; Höhne, T.; Mohammedi, B. et al.
    The capability of Ansys CFX to predict the mixing phenomena in ROCOM test facility
    SN Applied Sciences 1(2019), 1644 (10.1007/s42452-019-1574-1)
  • Höhne, T.; Rayya, A.; Montoya, G.
    Numerical modelling of horizontal oil-water pipe flow
    Energies 13(2020)19, 5042 (10.3390/en13195042)
  • Höhne, T.; Lucas, D.
    A multiscale approach simulating generic pool boiling
    Lecture (Conference):
    18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), 18.-23.08.2019, Portland, USA
  • Höhne, T.; Lucas, D.
    A multiscale approach simulating generic pool boiling
    Contribution to proceedings:
    18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), 18.-23.08.2019, Portland, USA
  • Höhne, T.; Lucas, D.
    A multiscale approach simulating generic pool boiling
    Nuclear Science and Engineering 194(2020)10, 859-872 (10.1080/00295639.2020.1764265)
  • Huang, M.; Höhne, T.
    Numerical simulation of multicomponent flows with the presence of density gradients for the upgrading of advanced turbulence models
    Nuclear Engineering and Design 344(2019), 28-37 (10.1016/j.nucengdes.2019.01.025)
  • Kliem, S.; Grahn, A.; Bilodid, Y. et al.
    A realistic approach for the assessment of the consequences of heterogeneous boron dilution events in pressurized water reactors
    Nuclear Engineering and Design 349(2019), 150-161 (10.1016/j.nucengdes.2019.04.038)
  • Hoehne, T.; Krepper, E.; Lucas, D. et al.
    A multiscale approach simulating boiling in a heated pipe including flow pattern transition
    Nuclear Technology 205(2019), 48-56 (10.1080/00295450.2018.1495025)
  • Höhne, T.; Gabriel, S.
    Simulation of a counter-current horizontal gas/liquid flow experiment at the WENKA channel using a droplet entrainment model
    Annals of Nuclear Energy 121(2018), 414-425 (10.1016/j.anucene.2018.07.047)
  • Höhne, T.; Kliem, S.; Bieder, U.
    IAEA CRP benchmark of ROCOM PTS test case for the use of CFD in reactor design using the CFD-codes ANSYS CFX and TRIOCFD
    Nuclear Engineering and Design 333(2018), 161-180 (10.1016/j.nucengdes.2018.04.017)
  • Höhne, T.; Krepper, E.; Lucas, D. et al.
    CFD-Simulation of boiling in a heated pipe including flow pattern transitions using the GENTOP concept
    Contribution to proceedings:
    The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), 03.-08.09.2017, Xian, China
  • Höhne, T.; Krepper, E.; Lucas, D. et al.
    CFD-Simulation of boiling in a heated pipe including flow pattern transitions using the GENTOP concept
    Nuclear Engineering and Design 322(2017), 165-176 (10.1016/j.nucengdes.2017.06.047)
  • Höhne, T.; Krepper, E.; Lucas, D. et al.
    CFD-Simulation of boiling in a heated pipe including flow pattern transitions using the GENTOP concept
    Lecture (Conference):
    The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), 03.-08.09.2017, Xian, China
  • Höhne, T.; Deendarlianto, A.
    Numerical simulation of full scale Upper Plenum Test Facility experiments
    Journal of Fluid Flow, Heat and Mass Transfer (JFFHMT) 4(2017), 19-34 (10.11159/jffhmt.2017.003)
  • Höhne, T.; Gasiunas, S.; Šeporaitis, M.
    Numerical Modelling of a Direct Contact Condensation Experiment using the AIAD Framework
    International Journal of Heat and Mass Transfer 111(2017), 211-222 (10.1016/j.ijheatmasstransfer.2017.03.104)
  • Höhne, T.; Porombka, P.
    Modelling horizontal two-phase flows using generalized models
    Annals of Nuclear Energy 111(2018), 311-316 (10.1016/j.anucene.2017.09.018)
  • Feng, Q.; Bieder, U.; Höhne, T.
    Analysis of buoyancy-driven flow in the ROCOM test facility
    Contribution to proceedings:
    IYNC2016 - International Youth Nuclear Congress, 24.-30.07.2016, Hangzhou, China
  • Feng, Q.; Bieder, U.; Höhne, T.
    Analysis of buoyancy-driven flow in the ROCOM test facility
    Energy Procedia 127(2017), 44-53 (10.1016/j.egypro.2017.08.062)
  • Porombka, P.; Höhne, T.
    Drag and turbulence modelling for free surface flows within the two-fluid Euler-Euler framework
    Chemical Engineering Science 134(2015), 348-359 (10.1016/j.ces.2015.05.029)
  • Höhne, T.; Geissler, T.; Bieberle, A. et al.
    Numerical modeling of a horizontal annular flow experiment using a droplet entrainment model
    Annals of Nuclear Energy 77(2015), 351-360 (10.1016/j.anucene.2014.11.041)
  • Fischer, K. C.; Höhne, T.; Hollands, T. et al.
    AMNT 2014: Key Topic Reactor Operation, Safety - Report Part 2
    atw - International Journal for Nuclear Power 59(2014)12, 701-702
  • Höhne, T.; Hänsch, S.
    A droplet entrainment model for horizontal segregated flows
    Nuclear Engineering and Design 286(2015), 18-26 (10.1016/j.nucengdes.2015.01.013)
  • Höhne, T.; Hänsch, S.
    A droplet entrainment model for horizontal segregated flows
    Contribution to proceedings:
    ANSYS Conference & 32. CADFEM Users´ Meeting 2014 (ACUM), 04.-06.06.2014, Nürnberg, Deutschland
    CD-ROM
  • Höhne, T.; Hänsch, S.
    A droplet entrainment model for horizontal segregated flows
    Invited lecture (Conferences):
    ANSYS Conference & 32. CADFEM Users´ Meeting 2014 (ACUM), 04.-06.06.2014, Nürnberg, Deutschland
  • Hänsch, S.; Lucas, D.; Höhne, T. et al.
    Application of a new concept for multi-scale interfacial structures to the dam-break case with an obstacle
    Nuclear Engineering and Design 279(2014), 171-181 (10.1016/j.nucengdes.2014.02.006)
  • Höhne, T.; Mehlhoop, J.-P.
    Validation of closure models for interfacial drag and turbulence in numerical simulations of horizontal stratified gas-liquid flows
    International Journal of Multiphase Flow 62(2014), 1-16 (10.1016/j.ijmultiphaseflow.2014.01.012)
  • Höhne, T.
    Thermal-Hydraulic Investigations for Safety Related Tasks
    atw - International Journal for Nuclear Power 58(2013)10, 587-588
  • Höhne, T.
    Scale Resolved Simulations of the OECD/NEA−Vattenfall T-Junction Benchmark using LES methods
    Nuclear Engineering and Design 269(2014), 149-154 (10.1016/j.nucengdes.2013.08.021)
  • Stieglitz, R.; Mull, T.; Höhne, T. et al.
    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
    Lecture (Conference):
    5th Latin American CFD Workshop Applied to the Oil and Gas Industry, 10.-11.07.2012, Rio de Janeiro, Brasilien
  • Höhne, T.
    Development and validation of a morphology detection algorithm (AIAD) for horizontal two phase flows
    Contribution to proceedings:
    5th Latin American CFD Workshop Applied to the Oil and Gas Industry, 10.-11.07.2012, Rio de Janeiro, Brasilien
    CD-ROM
  • Höhne, T.
    Development and validation of a morphology detection algorithm (AIAD) for horizontal two phase flows
    Petrobras Technical Bulletin (2016)
  • Lucas, D.; Coste, P.; Höhne, T. et al.
    CFD modeling of free surface flow with and without condensation
    Multiphase Science and Technology 23(2011), 253-342 (10.1615/MultScienTechn.v23.i2-4.60)
  • Hänsch, S.; Lucas, D.; Krepper, E. et al.
    A multi-field two-fluid concept for transitions between different scales of interfacial structures
    International Journal of Multiphase Flow 47(2012), 171-182 (10.1016/j.ijmultiphaseflow.2012.07.007)
  • Höhne, T.; Grahn, A.; Kliem, S. et al.
    Numerical simulation of the insulation material transport in a PWR core under loss of coolant conditions
    Nuclear Engineering and Design 258(2013), 241-248 (10.1016/j.nucengdes.2013.02.001)
  • 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 (10.1260/1757-482X.4.3.271)
  • Montoya, G.; Deendarlianto; Lucas, D. et al.
    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 (10.1155/2012/209542)
  • Prayitno, S.; Santoso, R.; Darlianto, D. et al.
    Counter-current Flow Limitation of Gas-Liquid Two phase Flow in Nearly Horizontal Pipe
    Science and Technology of Nuclear Installations (2012), 513809 (10.1155/2012/513809)
  • 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 (DOI: 10.1002/cite.201100035)
  • 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 (10.1155/2012/608678)
  • Deendarlianto; Höhne, T.; Apanasevich, P. et al.
    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 (10.1016/j.anucene.2011.09.010)
  • Deendarlianto; Höhne, T.; Lucas, D. et al.
    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 (10.1016/j.nucengdes.2011.08.071)
  • Deendarlianto; Höhne, T.; Lucas, D. et al.
    Gas-liquid countercurrent two-phase flow in a PWR hot leg: a comprehensive research review
    Nuclear Engineering and Design 243(2012), 214-233 (doi:10.1016/j.nucengdes.2011.11.015)
  • Höhne, T.; Grahn, A.; Kliem, S. et al.
    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 (doi:10.1016/j.ijheatfluidflow.2011.05.007)
  • 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 (:10.1016/j.nucengdes.2010.03.023)
  • Moretti, F.; Melideo, D.; Del Nevo, A. et al.
    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 (doi:10.1016/j.nucengdes.2011.05.005)
  • Höhne, T.; Vallee, C.
    Experiments and numerical simulations of horizontal two-phase flow regimes using an interfacial area density model
    Contribution to proceedings:
    ANSYS Conference & 28. CADFEM Users´ Meeting 2010, 03.-05.11.2010, Aachen, Deutschland
    CD-ROM
  • Höhne, T.; Vallee, C.
    Experiments and numerical simulations of horizontal two-phase flow regimes using an interfacial area density model
    Invited lecture (Conferences):
    ANSYS Conference & 28. CADFEM Users´ Meeting 2010, 03.-05.11.2010, Aachen, Deutschland
  • Höhne, T.; Vallee, 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.; 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. et al.
    Nachrechnung der Leistungsparameter eines Sicherheitsventils mit ANSYS CFX
    Forschung im Ingenieurwesen - Engineering Research 73(2009)2, 99-103 (10.1007/s10010-009-0096-1)
  • 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
  • Höhne, T.; Vallee, C.
    Modelling of stratified two phase flows using an interfacial area density model
    Lecture (Conference):
    Fifth International Conference on Computational and Experimental Methods in Multiphase and Complex Flow, 15.-17.06.2009, New Forest, Großbritannien
  • Höhne, T.; Vallee, C.
    Modelling of stratified two phase flows using an interfacial area density model
    Contribution to proceedings:
    Fifth International Conference on Computational and Experimental Methods in Multiphase and Complex Flow, 15.-17.06.2009, New Forest, Großbritannien
    CD-ROM
  • Da Silva, M. J.; Thiele, S.; Höhne, T. et al.
    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. et al.
    Sizing of safety valves using ANSYS CFX-Flo
    Chemical Engineering & Technology 32(2009)2, 1-6 (DOI: 10.1002/ceat.200800530)
  • 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 (doi:10.1155/2009/835162)
  • Höhne, T.; Moncalvo, D.; Friedel, L. et al.
    Nachrechnung eines Vollhub-Feder-Sicherheitsventils mit ANSYS CFX
    Contribution to proceedings:
    9. Fachtagung "Anlagen-, Arbeits- und Umweltsicherheit", 06.-07.11.2008, Köthen, Deutschland
  • Höhne, T.; Moncalvo, D.; Friedel, L. et al.
    Nachrechnung eines Vollhub-Feder-Sicherheitsventils mit ANSYS CFX
    Lecture (Conference):
    9. Fachtagung "Anlagen-, Arbeits- und Umweltsicherheit", 06.-07.11.2008, Köthen, Deutschland
  • Höhne, T.; Moncalvo, D.; Friedel, L. et al.
    Nachrechnung eines Vollhub-Feder-Sicherheitsventils mit ANSYS CFX
    Forschung im Ingenieurwesen - Engineering Research 73(2009)2, 99-103 (DOI: 10.1007/s10010-009-0096-1)
  • Moretti, F.; Melideo, D.; Del Nevo, A. et al.
    CFD validation against slug mixing experiment
    Science and Technology of Nuclear Installations (2009), Article ID 436218 (doi:10.1155/2009/436218)
  • Kliem, S.; Höhne, T.; Rohde, U. et al.
    Experiments on slug mixing under natural circulation conditions at the ROCOM test facility using high resolution measurement technique and numerical modeling
    Lecture (Conference):
    XCFD4NRS - Experiments and CFD Codes Application to Nuclear Reactor Safety, 10.-12.09.2008, Grenoble, France
  • Kliem, S.; Höhne, T.; Rohde, U. et al.
    Experiments on slug mixing under natural circulation conditions at the ROCOM test facility using high resolution measurement technique and numerical modeling
    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
  • Kliem, S.; Höhne, T.; Rohde, U. et al.
    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 (doi:10.1016/j.nucengdes.2009.11.015)
  • Rohde, U.; Höhne, T.; Krepper, E. et al.
    Application of CFD codes in nuclear reactor safety analysis
    Invited lecture (Conferences):
    TOPSAFE 2008, 01.-03.10.2008, Dubrovnik, Kroatia
  • Rohde, U.; Höhne, T.; Krepper, E. et al.
    Application of CFD codes in nuclear reactor safety analysis
    Contribution to proceedings:
    TOPSAFE 2008, 01.-03.10.2008, Dubrovnik, Kroatia
    CD-ROM. paper 099
  • Rohde, U.; Höhne, T.; Krepper, E. et al.
    Application of CFD codes in nuclear reactor safety analysis
    Science and Technology of Nuclear Installations 2010(2010), Article ID 198758 (doi:10.1155/2010/198758)
  • Bartosiewicz, Y.; Seynhaeve, J.-M.; Vallee, C. et al.
    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 (doi:10.1016/j.nucengdes.2010.04.032)
  • Bartosiewicz, Y.; Seynhaeve, J.-M.; Vallee, C. et al.
    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
    Lecture (Conference):
    XCFD4NRS - Experiments and CFD Code Applications to Nuclear Reactor Safety, 10.-12.09.2008, Grenoble, France
  • Bartosiewicz, Y.; Seynhaeve, J.-M.; Vallee, C. et al.
    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
    Contribution to proceedings:
    XCFD4NRS - Experiments and CFD Code Applications to Nuclear Reactor Safety, 10.-12.09.2008, Grenoble, France
    Paper HOR-01
  • Höhne, T.; Kliem, S.; Vaibar, R.
    Experimental and numerical modeling of transition matrix from momentum to buoyancy-driven flow in a pressurized water reactor
    Contribution to proceedings:
    16th International Conference on Nuclear Engineering ICONE16, 11.-15.05.2008, Orlando, USA
    CD_ROM, 48490
  • Höhne, T.; Kliem, S.; Vaibar, R.
    Experimental and numerical modeling of transition matrix from momentum to buoyancy-driven flow in a pressurized water reactor
    Lecture (Conference):
    16th International Conference on Nuclear Engineering ICONE16, 11.-15.05.2008, Orlando, USA
  • 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 (DOI: 10.1115/1.2983137)
  • Kliem, S.; Hemström, B.; Bezrukov, Y. et al.
    Comparative evaluation of coolant mixing experiments at the ROCOM, Vattenfall, and Gidropress test facilities
    Lecture (Conference):
    Annual Meeting of the AER Working Group D, 08.-09.05.2007, Paris, France
  • Kliem, S.; Hemström, B.; Bezrukov, Y. et al.
    Comparative evaluation of coolant mixing experiments at the ROCOM, Vattenfall, and Gidropress test facilities
    Science and Technology of Nuclear Installations 2007(2007), 25950 (doi:10.1155/2007/25950)
  • 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 (10.1504/IJNEST.2007.017080)
  • 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. et al.
    CFX simulations of ROCOM slug mixing experiments
    Journal of Power and Energy Systems 2(2008)2, 720-733 (10.1299/jpes.2.720)
  • Moretti, F.; Melideo, D.; D’Auria, F. et al.
    CFX simulations of ROCOM slug mixing experiments
    Contribution to proceedings:
    15th International Conference on Nuclear Engineering (ICONE15), 22.-26.04.2007, Nagoya, Japan
    ICONE15-10461
  • Moretti, F.; Melideo, D.; D’Auria, F. et al.
    CFX simulations of ROCOM slug mixing experiments
    Lecture (Conference):
    15th International Conference on Nuclear Engineering (ICONE15), 22.-26.04.2007, Nagoya, Japan
  • Höhne, T.; Kliem, S.; Rohde, U. et al.
    Boron Dilution Transients during natural circulation flow in PWR – experiments and CFD simulations
    Nuclear Engineering and Design 238(2008), 1987-1995 (10.1016/j.nucengdes.2007.10.032)
  • Rohde, U.; Höhne, T.; Kliem, S. et al.
    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 (doi:10.1016/j.nucengdes.2007.03.015)
  • Cartland Glover, G. M.; Höhne, T.; Kliem, S. et al.
    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 (10.1016/j.nucengdes.2006.08.010)
  • 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. et al.
    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. et al.
    Experiments at the mixing test facility ROCOM for benchmarking of CFD-codes
    Lecture (Conference):
    OECD/NEA & IAEA Workshop: "Benchmarking of CFD Codes for Application to Nuclear Reactor Safety", 05.-07.09.2006, Garching, Germany
  • Kliem, S.; Sühnel, T.; Rohde, U. et al.
    Experiments at the mixing test facility ROCOM for benchmarking of CFD-codes
    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
  • Kliem, S.; Sühnel, T.; Rohde, U. et al.
    Experiments at the mixing test facility ROCOM for benchmarking of CFD-codes
    Nuclear Engineering and Design 238(2008), 566-576 (10.1016/j.nucengdes.2007.02.053)
  • Vallee, C.; Höhne, T.; Prasser, H.-M. et al.
    Experimental investigation and CFD simulation of horizontal stratified two-phase flow phenomena
    Contribution to proceedings:
    CFD4NRS - Benchmarking of CFD Codes for Application to Nuclear Reactor Safety, 05.-07.09.2006, Garching, München, Germany
    Paper A6-31
  • Vallee, C.; Höhne, T.; Prasser, H.-M. et al.
    Experimental investigation and CFD simulation of horizontal stratified two-phase flow phenomena
    Nuclear Engineering and Design 238(2008), 637-646 (10.1016/j.nucengdes.2007.02.051)
  • Vallee, C.; Höhne, T.; Prasser, H.-M. et al.
    Experimental investigation and CFD simulation of horizontal stratified two-phase flow phenomena
    Lecture (Conference):
    CFD4NRS - Benchmarking of CFD Codes for Application to Nuclear Reactor Safety, 05.-07.09.2006, Garching, München, Germany
  • Rohde, U.; Höhne, T.; Kliem, S.
    Simulating turbulent mixing in nuclear reactor pressure vessels
    ANSYS Solutions 7(2006)2, 27-28
  • Vallee, C.; Höhne, T.; Prasser, H.-M. et al.
    Experimental investigation and CFD simulation of horizontal air/water slug flow
    Kerntechnik 71(2006)3, 95-103
  • Kliem, S.; Kozmenkov, Y.; Höhne, T. et al.
    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 (10.1016/j.pnucene.2006.06.008)
  • 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 (10.1016/j.nucengdes.2005.12.005)
  • Rohde, U.; Kliem, S.; Höhne, T. et al.
    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. et al.
    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. et al.
    Coolant mixing in a PWR - deboration transients, steam line breaks and emergency core cooling injection - experiments and analyses
    Contribution to proceedings:
    International Congress on Advanced Nuclear Power Plants (ICAPP), June 9-13, 2002 - Hollywood Florida, USA, Proc. CD-ROM, paper #1214.
  • Prasser, H.-M.; Grunwald, G.; Höhne, T. et al.
    Coolant mixing in a PWR - deboration transients, steam line breaks and emergency core cooling injection - experiments and analyses
    Lecture (Conference):
    International Congress on Advanced Nuclear Power Plants (ICAPP), June 9-13, 2002 - Hollywood Florida, USA, Proc. CD-ROM, paper #1214.
  • Prasser, H.-M.; Grunwald, G.; Höhne, T. et al.
    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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