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C. Morel, S. Mimouni, J. Lavieville, M. Boucker, 'R113 boiling bubbly flow in an annular geometry simulated with the NEPTUNE code', 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11), Avignon, France, October 3-6, 2005
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W. Yao, P. Coste, D. Bestion, M. Boucker, 'Two-Phase Pressurised Thermal Shock investigations using a 3D 2-Fluid Modelling of stratified Flow with Condensation', 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9, 2003
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OECD/CSNI, Proceedings of 'OECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes: Current and Future Applications', Barcelona, Spain, 2000
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D. Bestion, 'System code models and capabilities', CSNI Workshop THICKET-2004, Seminar on Transfer of Competence, Knowledge and Experience Gained through CSNI Activities in the Field of Thermal-hydraulics, Saclay, France, 7 - 11 June 2004
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D. Bestion, C. Morel, 'Strategy for improving two-phase 3-D modelling for nuclear safety applications', Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH) Oct 99, San Francisco
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D. Bestion, A. Latrobe, H. Paillere,A. Laporta, V. Teschendorff, H. Staedtke, N. Aksan, F. D'Auria, J. Vihavainen, P. Meloni, G. Hewitt, J. Lillington, B. Mavko, A. Prosek, J. Macek, M. Malacka, F. Camous, F. Fichot, D. Monhardt, 'European Project for Future Advances in Science and Technology for Nuclear Engineering Thermal-Hydraulics(EUROFASTNET)', Final Report, 2002
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D. Bestion, H. Paillere, A. Latrobe, A. Laporta, V. Teschendorff, H. Stadtke, N. Aksan, F. d'Auria, J. Vihavainen, P. Meloni, G. Hewitt, J. Lillington, A. Prosek, B. Mavko, J. Macek, M. Malacka, F. Camous, F. Fichot, D. Monhardt, 'EUROpean project for Future Advances in Sciences and Technology for Nuclear Engineering Thermal-Hydraulics (EUROFASTNET)', FISA 2003 ? EU Research in Reactor Safety, Conclusion Symposium on Shared Cost and Concerted Actions, 10-13 November 2003, EC Luxembourg
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C. Morel, A. Laporta, D. Bestion, O. Lebaigue, 'From the Direct Numerical Simulation to Averaged Two-Fluid Models. How different Types of Models Can Contribute to the Next Generation of Codes ?', CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes, Barcelona, Spain, April, 2000
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D. Bestion, 'On the application of two-phase CFD to Nuclear Reactor Thermalhydraulics', 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11), Avignon, France, October 3-6, 2005
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T. Hibiki, M. Ishii, 'Two-group interfacial area transport equations at bubbly-to-slug flow transition', Nucl. Eng. And Design 202 (1), 39-76, 2000
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S. Jayanti, M. Valette, 'Prediction of dry out and post-dry out heat transfer at high pressurse using a one-dimensional three-fluid model', Int. J. Heat Mass Transfer, 47 ,4895-4910, 2004
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D. Bestion, P. Clement, J.P. Caminade, J.M. Delhaye, P.Dumaz, J. Garnier, D. Grand, E. Hervieu, O. Lebaigue, H.Lemonnier, C. Lhuillier, J.R. Pages, Toumi, M. Villand,'FASTNET, A proposal for a ten-year effort in Thermal-Hydraulic research', Multiphase Science & Technology,Vol. 11, pp. 79-145, 1999, Editors: J.M. Delhaye, J. Garnier
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D. Lakehal, B. Smith, M. Milelli, 'Large-Eddy Simulation of Bubble Turbulent Shear Flows', IOP Journal of Turbulence, 3(25), 1-21, 2002
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D. Lakehal, S. Reboux, P. Liovic, 'Subgrid scale modeling for the LES of interfacial gas-liquid flows', 177eme Session du comite scientifique et technique de la Societe Hydrotechnique de France, Advances in the modelling methodologies of two-phase flows, Lyons, France, November 24-26, 2004
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T. Hibiki, M. Ishii, 'One-group interfacial area transport of bubbly flows in vertical round tubes', I. J. Heat and Mass Transfer 43 2711-2723, 2000
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W. Yao, C. Morel, 'Volumetric interfacial area prediction in upward bubbly two-phase flow', Int. J. Heat and Mass Transfer 47, 307-328, 2004
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B. Mathieu, 'Etudes physique, experimentale et numerique des mecanismes de base intervenant dans les ecoulements diphasiques', These de doctorat Universite de Provence, Mention : Sciences Specialite : Mecanique-Energetique, 20 novembre 2003
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E. Labourasse, A. Toutant, O. Lebaigue, 'Bubble interface-turbulence interaction', 5th International Conference of Multiphase Flow (ICMF 2004), Yokohama, Japan, 31st May - 3rd June 2004
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23 |
M. Chandesris, G. Serre, 'One dimensional averaged (k-e) turbulence model applied to channel, pipe and rod bundle flows', 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11), Avignon, France, October 3-6, 2005
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M. Scheuerer, F. Menter, I. Toth, A. Latrobe, A. Martin, E. Krepper, S. Willemsen, P. Muhlbauer, M. Andreani, R. Karlsson, I. Karppinen, G. Kimber, 'Evaluation of computational fluid dynamic methods for reactor safety analyses (ECORA)', FISA 2003 ? EU Research in Reactor Safety, Conclusion Symposium on Shared Cost and Concerted Actions, 10-13 November 2003, EC Luxembourg
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D. Bestion, C. Morel, W. Yao, P. Coste, M. Boucker, A. Laporta, 'First experience in developing and applying the NEPTUNE code a two-phase CFD tool for Reactor Safety Analysis', Technical Meeting On Use of Computational Fluid Dynamics (CFD) Codes for Safety Analysis of Reactor Systems, including Containment, Pisa, Italy, 11?15 November 2002
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D. Jamet, P. Ruyer, 'A quasi-incompressible model dedicated to the Direct Numerical Simulation of liquid-vapour flow with phase change', 5th Int. Conf. on Multiphase Flow, Yokohama, Japan, May 30-June 4, 2004
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B. Mathieu, O. Lebaigue ,L Tadrist, 'Influence of a dynamic contact line model on the characteristics of nucleate wall boiling computed with a DNS approach', 5th International Conference of Multiphase Flow (ICMF 2004), Yokohama, Japan, 31st May - 3rd June 2004
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G. Serre, D. Bestion, 'Progress in Improving two-fluid model in system code using turbulence and interfacial area equations', 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11), Avignon, France, October 3-6, 2005
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31 |
H. Paillere, A. Kumbaro, J. Garcia-Cascales, D. Bestion, S. Mimouni, A. Laporta, H. Stadtke, G. Franchello, U. Graf, P. Romstedt, E.F. Toro, E. Romenski, H. Deconinck, E. Valero,M. Ricchiuto, F. De Cachard, B. Smith, 'Advanced 3D Two-Phase Flow Simulation Tool for Application to Reactor Safety (ASTAR)', FISA 2003 ? EU Research in Reactor Safety, Conclusion Symposium on Shared Cost and Concerted Actions, 10-13 November 2003, EC Luxembourg
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P. Peturaud, E. Hervieu, 'Physical validation of the NEPTUNE two-phase modelling: validation plan to be adopted, experimental program to be set up, and associated instrumentation techniques developed', 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11), Avignon, France, October 3-6, 2005
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33 |
C. Morel, Wei Yao, D. Bestion, 'Three Dimensional modelling of boiling flow', 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9, 2003
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C. Morel, 'Turbulence modelling and first numerical simulations in turbulent two-phase flows', 11th Symposium on Turbulent Shear Flows, Vol. 3, Poster Session 3, pp. 3-10, 3-15, Grenoble, France, September 8-10., 1997
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J. Garnier, E. Manon, G. Cubizolles, Local measurement of flow boiling of refrigerant 12 in a vertical tube, Multiphase Science and Technology, Vol 13 pp 1-111, 2001
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A. Guelfi, S. Pitot, THYC (ThermoHYdraulique des Composants) Version 4.1 - Note de Principe , EDF R&D Internal Report HI-84-03-020A, 2004
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M. Grandotto, J.L. Cheissoux, J.P. Gaillard, E. de Langre, P. Obry, M. Bernard, 'A 3-D finite Element code for two-phase flow analysis in PWR steam generators', European Two- Phase Flow Group meeting, JRC-ISPRA, 21-24 may 1990, Varese, Italy
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I. Toumi, A. Bergeron, D. Gallo, E. Royer, D. Caruge, 'Flica 4 a three-dimensional two-phase flow computer code with advanced numerical methods for nuclear applications', Nuclear Engineering and Design, 200, 2000
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A. Guelfi, M. Boucker, JM. Herard, P. Peturaud, D. Bestion, P. Boudier, P. Fillion, M. Grandotto, E. Hervieu, 'A New Multi-Scale Platform for Advanced Nuclear Thermal-Hydraulics-Status and Prospects of the NEPTUNE Project', 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11), Avignon, France, October 3-6, 2005
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