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Science and Technology of Nuclear Installations
Volume 2010 (2010), Article ID 470794, 14 pages
http://dx.doi.org/10.1155/2010/470794
Research Article

Investigation of a Coolant Mixing Phenomena within the Reactor Pressure Vessel of a VVER-1000 Reactor with Different Simulation Tools

1Forschungzentrum Karlsruhe GmbH (FZK), Institute of Neutron Physics and Reactor Technology (INR), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany
2Massaschusetts Institute of Technology, 77 Massachusetts Avenue, 24-215, Cambridge, MA 02139-4307, USA

Received 19 May 2009; Accepted 4 October 2009

Academic Editor: Dubravko Pevec

Copyright © 2010 V. Sánchez 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. R. Riemke, “RELAP5 multi-dimensional constitutive models,” in RELAP5/TRAC-B International Users Seminar, Baton Rouge, La, USA, November 1991.
  2. “TRAC-BF/MOD1: An advanced best-estimate computer program for BWR accident analysis,” US Nuclear Regulatory Commission Report NUREG/CR-4356-Vol.1, Idaho National Engineering Laboratory, August 1992.
  3. P. Bazin and M. Pelissier, “CATHARE 2 V25_1: description of the base revision 6.1 physical laws used in the 1D, 0D and 3D modules,” CEA/DER/SSTH/LDAS/EM/2005-038, 2006.
  4. U. Graf, “Implicit coupling of fluid-dynamic systems: application to multidimensional counter-current two-phase flow of water and steam,” Nuclear Science and Engineering, vol. 129, no. 3, pp. 305–310, 1998. View at Google Scholar
  5. F. Odar et al., “TRACE V4.0 User's Manual,” US NRC, 2005.
  6. N. Kolev, S. Aniel, E. Royer, U. Bieder, D. Popov, and Ts. Topalov, “The OECD VVER-1000 Coolant Transient Benchmark Phase 2 (V1000CT-2) Volume I: Specifications of the Coolant mixing problem,” NEA/NC DOC, 2004.
  7. ANSYS Inc., “ANSYS CFX Release 11.0,” Reference Guide, 2007.
  8. H. G. Joo, D. Barber, G. Jiang, and T. Downar, “PARCS: a multidimensional two-group reactor kinetics code based on the nonlinear analytical nodal method,” School of Nuclear Engineering, Purdue University, July 2002.
  9. W. Jaeger, W. Lischke, and V. H. Sánchez Espinoza, “Safety related investigations of the VVER-1000 reactor type by the coupled code system TRACE/PARCS,” in Proceedings 15th International Conference on Nuclear Engineering (ICONE '07), Nagoya, Japan, April 2007.
  10. V. Sánchez et al., “Analysis of the VVER-1000 coolant transient benchmark phase 1 with RELAP5/PARCS,” Progress of Nuclear Energy, vol. 48, pp. 865–879, 2006. View at Google Scholar
  11. B. Truong, “Application of RELAP5/PARCS coupled-code system in studying coolant mixing and main steam line break transients behavior of VVER-1000 reactor,” Tech. Rep., FZK, August 2006. View at Google Scholar
  12. M. Boettcher, “Investigations of the coolant mixing phenomena within reactor pressure vessel of the VVER-1000 reactor,” Nuclear Engineering and Design, vol. 238, pp. 445–545, 2008. View at Google Scholar
  13. N. Kolev et al., “Comparative analysis of exercise 2 results of the OECD VVER-1000 MSLB benchmark,” in Proceedings of the 16th Symposium of AER on VVER Reactor Physics and Safety, Bratislava, Slovak Republic, September 2006.