Science and Technology of Nuclear Installations
Volume 2009 (2009), Article ID 214512, 14 pages
doi:10.1155/2009/214512
Review Article

Review of Available Data for Validation of Nuresim Two-Phase CFD Software Applied to CHF Investigations

D. Bestion,1 H. Anglart,2 D. Caraghiaur,2 P. Péturaud,3 B. Smith,4 M. Andreani,4 B. Niceno,4 E. Krepper,5 D. Lucas,5 F. Moretti,6 M. C. Galassi,6 J. Macek,7 L. Vyskocil,7 B. Koncar,8 and G. Hazi9

1Commissariat à l'Énergie Atomique (CEA), DEN-DER-SSTH, 17 Rue des Martyrs, 38054 Grenoble, France
2Reactor Technology Division, Physics Department, Royal Institute of Technology (KTH), AlbaNova University center, 106 91 Stockholm, Sweden
3Électricité de France (EDF) R&D, Mécanique des Fluides Energie et Environnement, 6 quai Watier, 78401 Chatou, France
4Department of Nuclear Energy and Safety, Thermal-Hydraulics Laboratory, Paul Scherrer Institute (PSI), CH-5232 Villigen, Switzerland
5Forschungszentrum Dresden-Rossendorf (FZD) P.O.Box 510119, D-01314 Dresden, Germany
6Department of Mechanics, Nuclear and Production Engineering – DIMNP, Università di Pisa, 2, Via Diotisalvi, 56100 PISA, Italy
7Department of Thermal-Hydraulic Analyses, Nuclear Research Institute Rez plc (NRI), 25068 Rez, Czech Republic
8Josef Stefan Institute (JSI), Jamova 39, 1000 Ljubljana, Slovenia
9KFKI Atomic Energy Research Institute, Theoretical Thermohydraulics, Research Group, 1525 Budapest, Hungary

Received 24 January 2008; Accepted 23 May 2008

Academic Editor: Iztok Tiselj

Copyright © 2009 D. Bestion et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. D. Bestion, H. Paillère, A. Latrobe, et al., “EUROpean project for future advances in sciences and technology for nuclear engineering thermalhydraulics (EUROFASTNET),” in Proceedings of the EU Research in Reactor Safety, Conclusion Symposium on Shared Cost and Concerted Actions (FISA '03), EC Luxembourg, November 2003.
  2. H. Paillère, A. Kumbaro, J. Garcia-Cascales, et al., “Advanced 3D two-phase flow simulation tool for application to reactor safety (ASTAR),” in Proceedings of the EU Research in Reactor Safety, Conclusion Symposium on Shared Cost and Concerted Actions (FISA '03), EC Luxembourg, November 2003.
  3. M. Scheuerer, F. Menter, I. Tóth, et al., “Evaluation of computational fluid dynamic methods for reactor safety analyses (ECORA),” in Proceedings of the EU Research in Reactor Safety, Conclusion Symposium on Shared Cost and Concerted Actions (FISA '03), EC Luxembourg, November 2003.
  4. A. Guelfi, M. Boucker, J. M. Hérard, et al., “A new multi-scale platform for advanced nuclear thermalhydraulics status and prospects of the NEPTUNE project,” in Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-11), Avignon, France, October 2005.
  5. D. Bestion and A. Guelfi, “Status and perspective of two-phase flow modelling in the NEPTUNE multi-scale thermalhydraulic platform for nuclear reactor simulation,” Nuclear Engineering and Technology, vol. 37, no. 6, pp. 511–524, 2005.
  6. D. Bestion and A. Guelfi, “Multiscale analysis of nuclear reactors thermalhydraulics—the NEPTUNE project,” La Houille Blanche, no. 5, pp. 65–74, 2005.
  7. D. Bestion, H. Anglart, B. L. Smith, et al., “Extension of CFD codes to two-phase flow safety problems,” Technical Note, OECD Nuclear Energy Agency, Paris, France, 2006.
  8. C. Grossetête, Caractérisation expérimentale et simulations de l'évolution d'un écoulement diphasique à bulles ascendant dans une conduite verticale [Ph.D. thesis], Ecole Centrale Paris, Paris, France, 1995.
  9. C. Morel, Modélisation multidimensionnelle des écoulements diphasiques gaz-liquide—application à la simulation des écoulements à bulles en conduite verticale [Ph.D. thesis], Ecole Centrale Paris, Paris, France, 1997.
  10. W. Yao and C. Morel, “Volumetric interfacial area prediction in upward bubbly two-phase flow,” International Journal of Heat and Mass Transfer, vol. 47, no. 2, pp. 307–328, 2004. View at Publisher · View at Google Scholar
  11. J. Garnier, E. Manon, and G. Cubizolles, “Local measurements on flow boiling of refrigerant 12 in a vertical tube,” Multiphase Science and Technology, vol. 13, no. 1-2, pp. 1–111, 2001.
  12. C. Morel, Y. Wei, and D. Bestion, “Three dimensional modelling of boiling flow for the NEPTUNE code,” in Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-10), Seoul, Korea, October 2003.
  13. M. Boucker, A. Guelfi, S. Mimouni, P. Péturaud, D. Bestion, and E. Hervieu, “Towards the prediction of local thermal-hydraulics in real PWR core conditions using NEPTUNE_CFD software,” in Proceedings of the Workshop on Modelling and Measurements of Two-Phase Flows and Heat Transfer in Nuclear Fuel Assemblies, KTH, Stockholm, Sweden, October 2006.
  14. G. Serre and D. Bestion, “Progress in improving two-fluid model in system code using turbulence and interfacial area equations,” in Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-11), Avignon, France, October 2005.
  15. R. P. Roy, V. Velidandla, S. P. Kalra, and P. Peturaud, “Local measurements in the two-phase region of turbulent subcooled boiling flow,” Journal of Heat Transfer, vol. 116, no. 3, pp. 660–669, 1994. View at Publisher · View at Google Scholar
  16. R. P. Roy, V. Velidandla, and S. P. Kalra, “Velocity field in turbulent subcooled boiling flow,” Journal of Heat Transfer, vol. 119, no. 4, pp. 754–766, 1997. View at Publisher · View at Google Scholar
  17. R. P. Roy, S. Kang, J. A. Zarate, and A. Laporta, “Turbulent subcooled boiling flow—experiments and simulations,” Journal of Heat Transfer, vol. 124, no. 1, pp. 73–93, 2002. View at Publisher · View at Google Scholar
  18. S. Kang and R. P. Roy, “Vapor phase measurements in subcooled boiling flow,” Journal of Heat Transfer, vol. 124, no. 6, pp. 1207–1209, 2002. View at Publisher · View at Google Scholar
  19. C. Morel, S. Mimouni, M. Lavieville, and M. Boucker, “R113 boling bubbly flow in an annular geometry simulated with the NEPTUNE code,” in Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-11), Avignon, France, October 2005.
  20. M. D. Bartel, Experimental investigation of subcooled boiling [M.S.N.E. thesis], Purdue University, West Lafayette, Ind, USA, 1999.
  21. M. D. Bartel, M. Ishii, Y. Mi, T. Masukawa, R. Situ, and M. Mori, “Experimental investigation of subcooled boiling under BWR flow conditions,” in Proceedings of the 9th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-9), San Francisco, Calif, USA, October 1999.
  22. M. D. Bartel, M. Ishii, T. Masukawa, Y. Mi, and R. Situ, “Interfacial area measurements in subcooled flow boiling,” Nuclear Engineering and Design, vol. 210, no. 1–3, pp. 135–155, 2001. View at Publisher · View at Google Scholar
  23. R. Situ, T. Hibiki, X. Sun, Y. Mi, and M. Ishii, “Flow structure of subcooled boiling flow in an internally heated annulus,” International Journal of Heat and Mass Transfer, vol. 47, no. 24, pp. 5351–5364, 2004. View at Publisher · View at Google Scholar
  24. R. Situ, Y. Mi, M. Ishii, and M. Mori, “Photographic study of bubble behaviors in forced convection subcooled boiling,” International Journal of Heat and Mass Transfer, vol. 47, no. 17-18, pp. 3659–3667, 2004. View at Publisher · View at Google Scholar
  25. R. Situ, T. Hibiki, M. Ishii, and M. Mori, “Bubble lift-off size in forced convective subcooled boiling flow,” International Journal of Heat and Mass Transfer, vol. 48, no. 25-26, pp. 5536–5548, 2005. View at Publisher · View at Google Scholar
  26. B. Končar, I. Kljenak, and B. Mavko, “Modelling of local two-phase flow parameters in upward subcooled flow boiling at low pressure,” International Journal of Heat and Mass Transfer, vol. 47, no. 6-7, pp. 1499–1513, 2004. View at Publisher · View at Google Scholar
  27. B. Končar, I. Kljenak, and B. Mavko, “Nucleate boiling flow simulation with coupling of Eulerian and Lagrangian methods,” in Proceedings of the ASME Summer Heat Transfer Conference (HT '05), vol. 2, pp. 69–77, San Francisco, Calif, USA, July 2005.
  28. T. H. Lee, G. C. Park, and D. J. Lee, “Local flow characteristics of subcooled boiling flow of water in a vertical concentric annulus,” International Journal of Multiphase Flow, vol. 28, no. 8, pp. 1351–1368, 2002. View at Publisher · View at Google Scholar
  29. G. H. Yeoh and J. Y. Tu, “A bubble mechanistic model for subcooled boiling flow predictions,” Numerical Heat Transfer, Part B, vol. 45, no. 5, part B, pp. 475–493, 2004. View at Publisher · View at Google Scholar
  30. G. H. Yeoh and J. Y. Tu, “Thermal-hydrodynamic modeling of bubbly flows with heat and mass transfer,” AIChE Journal, vol. 51, no. 1, pp. 8–27, 2005. View at Publisher · View at Google Scholar
  31. G. H. Yeoh and J. Y. Tu, “A unified model considering force balances for departing vapour bubbles and population balance in subcooled boiling flow,” Nuclear Engineering and Design, vol. 235, no. 10–12, pp. 1251–1265, 2005. View at Publisher · View at Google Scholar
  32. J. Y. Tu, G. H. Yeoh, G.-C. Park, and M.-O. Kim, “On population balance approach for subcooled boiling flow prediction,” Journal of Heat Transfer, vol. 127, no. 3, pp. 253–264, 2005. View at Publisher · View at Google Scholar
  33. A. Schaffrath, A.-K. Krüssenberg, F.-P. Weiss, et al., “TOPFLOW—a new multipurpose thermalhydraulic test facility for the investigation of steady state and transient two phase flow phenomena,” Kerntechnik, vol. 66, no. 4, pp. 209–213, 2001.
  34. H.-M. Prasser, A. Böttger, and J. Zschau, “A new electrode-mesh tomograph for gas-liquid flows,” Flow Measurement and Instrumentation, vol. 9, no. 2, pp. 111–119, 1998. View at Publisher · View at Google Scholar
  35. H.-M. Prasser, E. Krepper, and D. Lucas, “Evolution of the two-phase flow in a vertical tube—decomposition of gas fraction profiles according to bubble size classes using wire-mesh sensors,” International Journal of Thermal Sciences, vol. 41, no. 1, pp. 17–28, 2002. View at Publisher · View at Google Scholar
  36. H.-M. Prasser, J. Zschau, D. Peters, G. Pietzsch, W. Taubert, and M. Trepte, “Fast wire-mesh sensors for gas-liquid flows—visualization with up to 10 000 frames per second,” in Proceedings of the International Congress on Advanced Nuclear Power Plants (ICAPP '02), Hollywood, Fla, USA, June 2002, paper # 1055.
  37. H.-M. Prasser, D. Scholz, and C. Zippe, “Bubble size measurement using wire-mesh sensors,” Flow Measurement and Instrumentation, vol. 12, no. 4, pp. 299–312, 2001. View at Publisher · View at Google Scholar
  38. A. Tomiyama, “Struggle with computational bubble dynamics,” in Proceedings of the 3rd International Conference on Multiphase Flow (ICMF'98), pp. 1–18, Lyon, France, June 1998.
  39. H.-M. Prasser, M. Beyer, A. Böttger, et al., “Influence of the pipe diameter on the structure of the gas-liquid interface in a vertical two-phase pipe flow,” in Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-10), Seoul, Korea, October 2003.
  40. D. Lucas and H.-M. Prasser, “Steam bubble condensation in sub-cooled water in case of co-current vertical pipe flow,” Nuclear Engineering and Design, vol. 237, no. 5, pp. 497–508, 2007. View at Publisher · View at Google Scholar
  41. A. Inoue, T. Kurosu, T. Aoki, M. Yagi, T. Mitsutake, and S. Morooka, “Void fraction distribution in BWR fuel assembly and evaluation of subchannel code,” Journal of Nuclear Science and Technology, vol. 32, no. 7, pp. 629–640, 1995. View at Publisher · View at Google Scholar
  42. B. Niceno, B. Smith, and M. T. Dhotre, “Euler-Euler large eddy simulation of a square cross section bubble column using the NURESIM CFD platform,” in Proceedings of the 12th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-12), Pittsburgh, Pa, USA, September-October 2007.
  43. B. Končar, “Use of two-phase wall function for simulation of boiling flow,” in Proceedings of the 12th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-12), Pittsburgh, Pa, USA, September-October 2007.
  44. D. Bestion, D. Caraghiaur, H. Anglart, et al., “Review of the existing data basis for the validation of models for CHF,” NURESIM Deliverable D2.2.1, http://www.nuresim.com.
  45. G. F. Hewitt, “Burnout,” in Handbook of Multiphase Systems, G. Hetsroni, Ed., pp. 66–141, Hemisphere, New York, NY, USA, 1982.
  46. K. M. Becker and A. Letzer, “An experimental study of the effect of the axial heat flux distribution on the dryout conditions in a 3650 mm long annulus,” International Journal of Multiphase Flow, vol. 7, no. 1, pp. 47–61, 1981. View at Publisher · View at Google Scholar
  47. P. Persson, “Measurements and analysis of dry out in annular geometry with two sided heating with uniform and nonuniform axial power and the influence of spacers and spacer positions,” SKI/KSU/KTH Project, 2001.
  48. J. Würtz, “An experimental and theoretical investigation of annular steam-water flow in tubes and annuli at 30 to 90 bar,” Risø Report, Risø National Laboratory, Roskilde, Denmark, 1978.
  49. T. Okawa, A. Kotani, and I. Kataoka, “Experiments for liquid phase mass transfer rate in annular regime for a small vertical tube,” International Journal of Heat and Mass Transfer, vol. 48, no. 3-4, pp. 585–598, 2005. View at Publisher · View at Google Scholar
  50. P. Andreussi, “Droplet transfer in two-phase annular flow,” International Journal of Multiphase Flow, vol. 9, no. 6, pp. 697–713, 1983. View at Publisher · View at Google Scholar
  51. C. J. Bates and J. M. Sheriff, “High data rate measurements of droplet dynamics in a vertical gas-liquid annular flow,” Flow Measurement and Instrumentation, vol. 3, no. 4, pp. 247–256, 1992. View at Publisher · View at Google Scholar
  52. A. H. Govan, G. F. Hewitt, D. G. Owen, and G. Burnett, “Wall shear stress measurements in vertical air-water annular two-phase flow,” International Journal of Multiphase Flow, vol. 15, no. 3, pp. 307–325, 1989. View at Publisher · View at Google Scholar
  53. L. B. Cousins and G. F. Hewitt, “Liquid phase mass transfer in annular two-phase flow: droplet deposition and liquid entrainment,” UKAEA Report, Atomic Energy Research Establishment, Harwell, UK, 1968.
  54. C. Adamsson and H. Anglart, “Experimental investigation of the liquid film for annular flow in a tube with various axial power distributions,” in Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-11), Avignon, France, October 2005.
  55. L. B. Fore, B. B. Ibrahim, and S. G. Beus, “Visual measurements of droplet size in gas-liquid annular flow,” International Journal of Multiphase Flow, vol. 28, no. 12, pp. 1895–1910, 2002. View at Publisher · View at Google Scholar
  56. L. B. Fore and A. E. Dukler, “The distribution of drop size and velocity in gas-liquid annular flow,” International Journal of Multiphase Flow, vol. 21, no. 2, pp. 137–149, 1995. View at Publisher · View at Google Scholar