Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2008 (2008), Article ID 732158, 8 pages
http://dx.doi.org/10.1155/2008/732158
Research Article

Simulation of Boiling Flow Experiments Close to CHF with the Neptune_CFD Code

Reactor Engineering Division, Jožef Stefan Institute, Jamova cesta 39, 1000 Ljubljana, Slovenia

Received 11 March 2008; Accepted 26 August 2008

Academic Editor: Ivo Kljenak

Copyright © 2008 Boštjan Končar and Borut Mavko. 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, D. Caraghiaur, H. Anglart et al., “Deliverable D2.2.1: Review of the Existing Data Basis for the Validation of Models for CHF,” NURESIM-SP2-TH D2.2.1., 2006.
  2. J. Laviéville, E. Quemerais, S. Mimouni, M. Boucker, and N. Mechitoua, Neptune CFD V1.0 Theory Manual, EDF, 2005.
  3. 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
  4. C. Morel, W. Yao, and D. Bestion, “Three dimensional modelling of boiling flow for the Neptune code,” in Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH '03), Seoul, Korea, October 2003.
  5. J. Garnier and F. François, DEBORA data bank (CD), 2006.
  6. M. Ishii and N. Zuber, “Drag coefficient and relative velocity in bubbly, droplet or particulate flows,” AIChE Journal, vol. 25, no. 5, pp. 843–855, 1979. View at Publisher · View at Google Scholar
  7. N. Zuber, “On the dispersed two-phase flow in the laminar flow regime,” Chemical Engineering Science, vol. 19, no. 11, pp. 897–917, 1964. View at Publisher · View at Google Scholar
  8. W. E. Ranz and W. R. Marshall Jr., “Evaporation from drops—part I,” Chemical Engineering Progress, vol. 48, no. 3, pp. 141–146, 1952. View at Google Scholar
  9. N. Kurul and M. Z. Podowski, “Multidimensional effects in forced convection subcooled boiling,” in Proceedings of the 9th International Heat Transfer Conference, vol. 2, pp. 21–26, Jerusalem, Israel, August 1990.
  10. B. Končar and E. Krepper, “CFD simulation of convective flow boiling of refrigerant in a vertical annulus,” Nuclear Engineering and Design, vol. 238, no. 3, pp. 693–706, 2008. View at Publisher · View at Google Scholar
  11. B. Končar, E. Krepper, and Y. Egorov, “CFD modelling of subcooled flow boiling for nuclear engineering applications,” in Proceedings of the International Conference on Nuclear Energy for New Europe, Bled, Slovenia, September 2005.
  12. J. M. Le Corre and S. C. Yao, “A mechanistic model of critical heat flux under subcooled flow boiling conditions for application to one and three-dimensional computer codes,” in Proceedings of the 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH '07), Pittsburgh, Pa, USA, September-October 2007.
  13. B. Končar, B. Mavko, and Y. A. Hassan, “Two-phase wall function for modeling of turbulent boundary layer in subcooled boiling flow,” in Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH '05), Avignon, France, October 2005.
  14. C. Morel, S. Mimouni, J. M. Laviéville, and M. Boucker, “R113 boiling bubbly flow in an annular geometry simulated with the Neptune code,” in Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH '05), Avignon, France, October 2005.
  15. F. Ramstorfer, B. Breitschädel, H. Steiner, and G. Brenn, “Modelling of the near-wall liquid velocity field in subcooled boiling flow,” in Proceedings of the ASME Summer Heat Transfer Conference (HT '05), vol. 2, pp. 323–332, San Francisco, Calif, USA, July 2005.