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P. Coste, J. Lavieville, J. Pouvreau, C. Baudry, M. Guingo, A. Douce, “Validation of the Large Interface Method of NEPTUNE_CFD 1.0.8 for Pressurized Thermal Shock (PTS) Applications”, Proc. XCFD4NRS, Washington DC, USA, 14-16 September 2010.
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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 (2009), Article ID 583259
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B. Niceno, M. Boucker, and B. L. Smith, Euler-Euler Large Eddy Simulation of a Square Cross-Sectional Bubble Column Using the Neptune_CFD Code, Science and Technology of Nuclear Installations, Volume 2009 (2009), Article ID 410272
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Mahaffy, J. (ed.) “Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications”, OECD, Nuclear Energy Agency, Technical Report, NEA/ CSN I /R(2007)5, April 2007
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Smith, B.L. (ed.), “Assessment of Computational Fluid Dynamics (CFD) for Nuclear Reactor Safety Problems”, OECD Nuclear Energy Agency, Technical Report, NEA/CSNI/R(2007)13, Jan. 2008.
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D. Bestion, (ed.), Extension of CFD Codes to Two-Phase Flow Safety Problems, NEA/SEN/SIN/AMA(2006)2
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D. Bestion, H. Anglart, J. Mahaffy, D. Lucas, C.H. Song, M. Scheuerer, G. Zigh, M. Andreani, F. Kasahara, M. Heitsch, E. Komen, F. Moretti, T. Morii, P. Mühlbauer, B.L. Smith, T. Watanabe, Extension of CFD Codes to Two-Phase Flow Safety Problems, NEA-CSNI-R(2010)2
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D. Caraghiaur and H. Anglart, Annular flow deposition model with obstacle effect, 6th Int. Conf. on multiphase Flow ICMF, 2007, Leipzig,, Germany, July 9-13
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D. Caraghiaur and H. Anglart, Lagrangian particle tracking as a tool for deposition modelling in annular flow, ICONE-17, july 12-17, 2009, Brussels, Belgium
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D. Bestion, H. Anglart, D. Caraghiaur, P. Peturaud, B. Smith, M. Andreani, B. Niceno, E. Krepper, D. Lucas, F. Moretti, M. C. Galassi, J. Macek, L. Vyskocil, B. Koncar, and G. Hazi, Review of Available Data for Validation of Nuresim Two-Phase CFD Software Applied to CHF Investigations, Science and Technology of Nuclear Installations, Volume 2009 (2009), Article ID 214512
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C. Morel and J. M. Lavieville, Modeling of Multisize Bubbly Flow and Application to the Simulation of Boiling Flows with the Neptune CFD Code, Science and Technology of Nuclear Installations, Volume 2009, Article ID 953527
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B. Koncar, E. Krepper, CFD simulation of convective flow boiling of refrigerant in a vertical annulus, Nucl. Eng. Des.,Volume 238, Issue 3, 2008, pp. 693-706
DOI
ScienceOn
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G. Bois, D. Jamet & O. Lebaigue, 2010, “Towards Large Eddy Simulation of two-phase flow with phase-change: Direct Numerical Simulation of a pseudo-turbulent twophase condensing flow”, 7th International Conference on Multiphase Flow, ICMF 2010, Tampa, FL, USA, May 30 – June 4, 2010
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Coste P., Pouvreau J., Morel C., Laviéville J., Boucker M., Martin A., “Modeling Turbulence and Friction around a Large Interface in a Three-Dimension Two-Velocity Eule-rian Code”, Proc. of Int. Conf. NURETH 12, Pittsburgh, USA, 30 Septembre- 4 Octobre 2007.
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S. Magdeleine, B. Mathieu, O. Lebaigue & C. Morel, 2010, “DNS up-scaling applied to volumetric interfacial area transport equation, 12 p., 7th International Conference on Multiphase Flow”, ICMF 2010, Tampa, FL, USA, May 30 – June 4, 2010.
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D. Lakehal: LEIS for the Prediction of Turbulent Multifluid Flows Applied to Thermal Hydraulics Applications. XCFD4NRS, Grenoble, Sep. 10-12, 2008
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Lakehal D., Fulgosi M., Banerjee S., Yadigaroglu G.,: Turbulence and heat transfer in condensing vapor-liquid flow, Phys. Fluids, 20, 065101, 2008.
DOI
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D. Bestion, Extension of CFD Code application to Two-Phase Flow Safety Problems, Nuclear Engineering and Technology, VOL.42, No.4, August 2010
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D. Bestion, Applicability of two-phase CFD to nuclear reactor thermalhydraulics and elaboration of Best Practice Guidelines, CFD4NRS-3, Washington-DC, sept. 2010
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NURESIM D2.2.1: Review of the existing data basis for the validation of CFD models for CHF, www.nuresim.com
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NURESIM D2.2.1.1c: Synthesis of the work performed in WP2.2 on CHF investigations using two-phase CFD, www.nuresim.com
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C. Morel, Wei Yao, D. Bestion, Three Dimensional modelling of boiling flow, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9, 2003
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J. Macek, L. Vyskocil, Simulation of Critical Heat Flux Experiments in NEPTUNE_CFD Code XCFD4NRS, Grenoble, France, 10 - 12 September 2008
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M. Boucker, A. Guelfi, S. Mimouni, P. Péturaud, D. Bestion, E. Hervieu, Towards the prediction of local thermalhydraulics in real PWR core conditions using NEPTUNE_CFD software, Workshop on Modeling and Measurements of Two-Phase Flows and Heat Transfer in Nuclear Fuel Assemblies, KTH, Stockholm, Sweden - 10-11 October 2006
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D. Lucas, E. Krepper, H.M. Prasser, Modelling of the evolution of large bubbly flow along a vertical pipe, 2007, Nuclear Technology 158, 291-303
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S. Mimouni, F. Archambeau, M. Boucker, J. Lavieville, CFD Modelling of subcooled boiling in the NEPTUNE_CFD code and application to fuel assembly analysis , XCFD4NRS, GRENOBLE, FRANCE, Sept10-12, 2008
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Proceedings of “OECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes: Current and Future Applications”, Barcelona (E), 2000
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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, I. 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. Bestion, A. Latrobe, H. Paillère, 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, and D. Monhardt, “European Project for Future Advances in Science and Technology for Nuclear Engineering Thermal-Hydraulics - EUROFASTNET, Final Report,” Technical Report, Commission of the European Communities, 2002.
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D. Bestion, A. Guelfi, « Status and perspective of twophase flow modelling in the NEPTUNE Multiscale thermalhydraulic platform for nuclear reactor simulation », Nuclear Engineering and Technology, 2005, Vol. 16, Nos 1-3, pp 1-5.
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A.Guelfi, D. Bestion, M. Boucker, P. Boudier, P. Fillion, M. Grandotto, J.M. Herrard, E. Hervieu, P. Peturaud, NEPTUNE A new Software Platform for advanced Reactor Thermalhydraulics, Nuclear Science and Engineering, 156, 282-324, 2007
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C. Chauliac, J.M. Aragonés, D. Bestion, D.G. Cacuci, N. Crouzet , F.P. Weiss, M. A. Zimmermann , NURESIM –A European simulation platform for nuclear reactor safety: multi-scale and multi-physics calculations, sensitivity and uncertainty analysis, FISA 2009, Praha, Czech Rep., June 22-24, 2009
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D. Bestion, D. Lucas, B. Smith, M. Boucker, M. Scheuerer, F. d’Auria, D. Lakehal, J. Macek, I. Tiselj, G. Hazi, V. Tanskanen, M. Ilvonen, N. Seiler, M. Boetcher, H. Anglart, Y. Bartosiewicz, Two-phase CFD advances in the NURESIM and NURISP projects , 18th International Conference on Nuclear Engineering ICONE 18, May 17-21, 2010, Xi’an, CHINA
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TRACE-V5.0, Theory Manual, 2007, TRACE V5.0 User Manual, 2007, TRACE V5.0 Assessment Manual, 2007
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M. Robert, M. Farvacque, M. Parent, and B. Faydide, “CATHARE 2 V2.5: A Fully Validated CATHARE Version for Various Applications,” Proc. 10th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH 10), Seoul, Republic of Korea, October 5–9, 2003.
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P. Emonot, A. Souyri, J.L. Gandrille, F. Barre, CATHARE 3: A new system code for thermal-hydraulic in the context of the NEPTUNE project, NURETH-13, Kanazawa City, Ishikawa Prefecture, Japan, September 27-October 2, 2009
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RELAP5/MOD3 Code Manual, Volume I: Code Structure, System Models and Solution Methods, NUREG/CR-5535, 1995
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38 |
M.J. Burwell, D. Enix, E. Lerchl, J. Miro, V. Teschendorff, and K. Wolfert, The Thermal-Hydraulic Code ATHLET for Analysis of PWR and BWR Systems, Fourth Int. Meeting on Nuclear Reactor Thermal-Hydraulics, NURETH-4, Proceedings Vol. 2, pp. 1234-1239, 1988
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Proceedings of OECD/CSNI Specialist Meeting on Transient Two-Phase Flow - System Thermalhydraulics, Aix-En-Provence (F), 1992
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Proceedings of OECD/CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements, 5-8 November 1996, Annapolis, Md, USA, NUREG/CP-0159, NEA/CSNI/R(97)4
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