Browse > Article
http://dx.doi.org/10.5516/NET.2010.42.6.608

FROM THE DIRECT NUMERICAL SIMULATION TO SYSTEM CODES - PERSPECTIVE FOR THE MULTI-SCALE ANALYSIS OF LWR THERMALHYDRAULICS  

Bestion, D. (CEA-Grenoble)
Publication Information
Nuclear Engineering and Technology / v.42, no.6, 2010 , pp. 608-619 More about this Journal
Abstract
A multi-scale analysis of water-cooled reactor thermalhydraulics can be used to take advantage of increased computer power and improved simulation tools, including Direct Numerical Simulation (DNS), Computational Fluid Dynamics (CFD) (in both open and porous mediums), and system thermalhydraulic codes. This paper presents a general strategy for this procedure for various thermalhydraulic scales. A short state of the art is given for each scale, and the role of the scale in the overall multi-scale analysis process is defined. System thermalhydraulic codes will remain a privileged tool for many investigations related to safety. CFD in porous medium is already being frequently used for core thermalhydraulics, either in 3D modules of system codes or in component codes. CFD in open medium allows zooming on some reactor components in specific situations, and may be coupled to the system and component scales. Various modeling approaches exist in the domain from DNS to CFD which may be used to improve the understanding of flow processes, and as a basis for developing more physically based models for macroscopic tools. A few examples are given to illustrate the multi-scale approach. Perspectives for the future are drawn from the present state of the art and directions for future research and development are given.
Keywords
Thermalhydraulics; System Code; CFD; Nuclear Reactor; Multi-Scale Analysis;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
Times Cited By Web Of Science : 0  (Related Records In Web of Science)
Times Cited By SCOPUS : 3
연도 인용수 순위
1 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.
2 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
3 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
4 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
5 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.
6 D. Bestion, (ed.), Extension of CFD Codes to Two-Phase Flow Safety Problems, NEA/SEN/SIN/AMA(2006)2
7 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
8 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
9 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
10 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
11 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
12 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
13 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
14 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.
15 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.
16 D. Lakehal: LEIS for the Prediction of Turbulent Multifluid Flows Applied to Thermal Hydraulics Applications. XCFD4NRS, Grenoble, Sep. 10-12, 2008
17 Lakehal D., Fulgosi M., Banerjee S., Yadigaroglu G.,: Turbulence and heat transfer in condensing vapor-liquid flow, Phys. Fluids, 20, 065101, 2008.   DOI
18 D. Bestion, Extension of CFD Code application to Two-Phase Flow Safety Problems, Nuclear Engineering and Technology, VOL.42, No.4, August 2010
19 D. Bestion, Applicability of two-phase CFD to nuclear reactor thermalhydraulics and elaboration of Best Practice Guidelines, CFD4NRS-3, Washington-DC, sept. 2010
20 NURESIM D2.2.1: Review of the existing data basis for the validation of CFD models for CHF, www.nuresim.com
21 NURESIM D2.2.1.1c: Synthesis of the work performed in WP2.2 on CHF investigations using two-phase CFD, www.nuresim.com
22 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
23 J. Macek, L. Vyskocil, Simulation of Critical Heat Flux Experiments in NEPTUNE_CFD Code XCFD4NRS, Grenoble, France, 10 - 12 September 2008
24 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
25 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
26 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
27 Proceedings of “OECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes: Current and Future Applications”, Barcelona (E), 2000
28 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
29 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.
30 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.
31 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
32 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
33 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
34 TRACE-V5.0, Theory Manual, 2007, TRACE V5.0 User Manual, 2007, TRACE V5.0 Assessment Manual, 2007
35 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.
36 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
37 RELAP5/MOD3 Code Manual, Volume I: Code Structure, System Models and Solution Methods, NUREG/CR-5535, 1995
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
39 Proceedings of OECD/CSNI Specialist Meeting on Transient Two-Phase Flow - System Thermalhydraulics, Aix-En-Provence (F), 1992
40 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