Thermal-Hydraulics of NPPs

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  • G. Yadigaroglu, & D. Lakehal,
    “Nuclear safety and thermal hydraulics: personal thoughts and some recent progress”, Nuclear Technology, in print (2016).
  • S. Thomas, C. Narayanan and D. Lakehal,
    “Validation Of 3D Simulations Of The NUPEC PSBT In Sub-channels Using TransAT”, Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-16), August 30-September 4, Chicago, Accepted for publication (2015)
  • J. Bao, S. Reboux, N. Pagan, and D. Lakehal,
    “Cathare-TransAT Coupling for the Prediction of Boron Dilution in the ROCOM Test Facility”, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), Chicago, USA, Aug. (2015)
  • D. Métrailler, S. Reboux and D. Lakehal,
    “Near-Wall Turbulence-Bubbles Interactions in a Channel Flow at Re=400: a DNS/LES Investigation”, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) Chicago, USA, Aug. (2015)
  • D. Métrailler, S. Reboux, D. Caviezel and D. Lakehal,
    “DNS of Turbulent Convective Flow Boiling in a Channel”, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), Chicago, USA, Aug. (2015)
  • D. Chatzikyriakou, J. Buongiorno, D. Caviezel, D. Lakehal,
    “DNS and LES or turbulent flow in a closed channel featuring a pattern of hemispherical roughness elements”, International Journal of Heat and Fluid Flow, 53 (2015) 29–43
  • A. Batta, et al.,
    “Experimental and numerical investigation of liquid-metal free-surface flows in spallation targets”, Nuclear Engineering and Design, 290 , pp. 107-118, 2015.
  • R. Ferry et al.,
    “Status and perspective of turbulence heat transfer modelling for the industrial application of liquid metal flows”, Nuclear Engineering and Design, 290 , pp. 99-106, 2015.
  • G. Yadigaroglu,
    “CMFD and the critical-heat-flux grand challenge in nuclear thermal–hydraulics – A letter to the Editor of this special issue”, Int. J. Multiphase Flow, 67, 3–12 (2014)
  • G. Yadigaroglu,
    “BWR Stability: History and State-of-the-Art,” keynote lecture, International Workshop on New Horizons in Nuclear Reactor Thermal Hydraulics and Safety, Bhabha Atomic Research Centre, Mumbai, India, January 13-15 (2014)
  • B. Askari and G. Yadigaroglu,
    “An advanced frequency-domain code for BWR stability analysis and design,” IMECE13, November 15-21, San Diego, California, USA, IMECE2013-65245 (2013)
  • G. Yadigaroglu,
    “Thermal-Hydraulic Issues and Achievements – A Historical Perspective”, invited lecture, The 15th International Topical Meeting on Nuclear Reactor Thermal – Hydraulics, NURETH-15. Pisa, Italy, 12-17 May (2013)
  • S. Gulati, C. Narayanan, J. Buongiorno, and D. Lakeha,
    “Simulation of Liquid Entrainment in Stratified and Annular Flow Regimes using Large-Eddy & Interface Simulation, LEIS”, 8th International Conference on Multiphase Flow (ICMF 2013), Korea, May (2013)
  • D. Caviezel, C. Narayanan, and D. Lakehal,
    “Large Eddy & Interface Simulation (LEIS) of turbulent flow and convective boiling in a PWR rod bundle”, 8th International Conference on Multiphase Flow (ICMF 2013), Korea, May (2013)
  • M. Labois, D. Lakehal,
    “Very-Large Eddy Simulation (V-LES) of the flow across a tube bundle”, Nuclear Engineering and Design 241, 2075–2085 (2011) Download Here
  • D. Lakehal, M. Labois,
    “A New modelling strategy for phase-change heat transfer in turbulent interfacial two-phase flow”, I. J. Multiphase Flow 37, 627–639 (2011) Download Here
  • M. Labois, C. Narayanan, D. Lakehal,
    “PTS Prediction using CMFD Code TransAT : The COSI test case. 3rd CFD4NRS Conf.”, OECD/NEA & IAEA Workshop, Washington, 14-16 Sep. (2010)
  • M. Labois, J. Panyasantisuk and T. Hohne,
    “On the Prediction of Boron Dilution in the Siemens PWR-prototpe ROCOM with the CMFD code TransAT”, Computational Fluid Dynamics (CFD) for Nuclear Reactor Safety Applications Workshop Proceedings, CFD4NRS-3, Bethesda, Maryland, USA, September 14-16, 2010CFD4NRS-3 (2010)
  • D. Chatzikyriakou, S.P. Walker, C.P. Hale, D. Lakehal and G.F. Hewitt,
    “Numerical and Experimental Investigation of the Heat Transfer of Non-Contacting Droplets During the Reflood Phase after a LOCA”, I. Heat Transfer Conf., ASME, Washington D.C., USA (2010)
  • D. Chatzikyriakou, S. P. Walker, B. Belhouachi, C. Narayanan, D. Lakehal and G. F. Hewitt,
    “Three Dimensional Modeling of the Hydrodynamics of Oblique Droplet-Hot Wall Interactions During the Reflood Phase After a LOCA.” J. Engineering for Gas Turbines and Power. 132 102914 (2010) Download Here
  • D. Lakehal.
    “LEIS for the prediction of turbulent multifluid flows applied to thermal-hydraulics applications” Nuclear Engineering and Design. 240 2096–2106 (2010)
  • Djamel Lakehal, Daniel Caviezel,
    “Large-Eddy Simulation of convective wall-boiling flow along an idealized PWR rod bundle”, Nuclear Engineering and Design, Available online 30 December 2016
  • M. Labois, D. Lakehal,
    “A level-Set based interfacial heat and mass transfer model built on TransAT: Application to pressurized thermal shock”, 7th I. Conf. Multiphase Flow, ICMF 2010, Tampa, FL, May 30 – June 4 (2010)
  • D. Lucas, D. Bestion, E. Bodele, P. Coste, M. Scheuerer , F. D’Auria , D. Mazzini, B. Smith, I. Tiselj, A. Martin, D. Lakehal, J.-M. Seynhaeve, R. Kyrki-Rajamaki, M. Ilvonen and J. Macek.
    “An Overview of the Pressurized Thermal Shock Issue in the Context of the NURESIM Project”. Science and Technology of Nuclear Installations, Volume 2009, Article ID 583259, 1-13 (2009)
  • D. Chatzikyriakoua, S.P. Walker, G.F. Hewitt, C. Narayanan, D. Lakehal,
    “Comparison of measured and modelled droplet–hot wall interactions”, Applied Thermal Engineering 29 (2009) Download Here
  • G. Yadigaroglu, M. Simiano, R. Milenkovic, J. Kubasch, M. Milelli, R. Zboray, F. De Cachard, B. Smith, D. Lakehal and B. Sigg,
    “CFD4NRS with a focus on experimental and CMFD investigations of bubbly flows.” Nuclear Engineering and Design 238, no. 3: 771-785 (2008)
  • V. Tanskanen, D. Lakehal and M. Puustinen,
    “Validation of direct contact condensation CFD models against condensation pool experiment”, Proceedings of Experiments and CFD Code Applications to Nuclear Reactor Safety, XCFD4NRS OECD, Grenoble, France, September 12-15, 1-12 (2008)
  • Junfeng Yang, Chidambaram Narayanan, Djamel Lakehal,
    “Large Eddy & Interface Simulation (LEIS) of disturbance waves and heat transfer in annular flows”, Nuclear Engineering and Design, Available online 19 November 2016
  • P. Liovic and D. Lakehal,
    “Interface-turbulence interactions in large-scale bubbling processes”, Int. J. Heat and Fluid Flow, 28, pp. 127-144 (2007)
  • D. Lucas et al.,
    “On the simulation of two-phase flow pressurized thermal shock (PTS)”, 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12) (2007)
  • D. Métrailler, S. Reboux, D. Lakehal,
    “Near-wall turbulence-bubbles interactions in a channel flow at Reτ = 400: A DNS investigation”, Nuclear Engineering and Design, Available online 10 November 2016
  • G. Yadigaroglu and D. Lakehal,
    “New challenges in computational thermal hydraulics”, Nuclear Technology, 152(2), 239-251 (2005)