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Science and Technology of Nuclear Installations
Volume 2009 (2009), Article ID 835162, 7 pages
Research Article

CFD Simulation of Thermal-Hydraulic Benchmark V1000CT-2 Using ANSYS CFX

Forschungszentrum Dresden-Rossendorf (FZD), Institute of Safety Research, P.O. Box 510119, 01314 Dresden, Germany

Received 16 July 2008; Revised 20 October 2008; Accepted 11 January 2009

Academic Editor: Bousbia Salah Anis

Copyright © 2009 Thomas Höhne. 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. B. Ivanov, K. Ivanov, P. Groudev, M. Pavlova, and V. Hadjev, “VVER-1000 Coolant Transient Benchmark Volume I: Main Coolant Pump switch on NEA/OECD NEA/NSC/DOC(2002)6,” 2003. View at Google Scholar
  2. N. Kolev, A. Milev, E. Royer, U. Bieder, D. Popov, and Ts. Tapalov, “VVER-1000 Coolant Transient Benchmark Volume II: Specifications of the RPV Coolant Mixing Problem NEA/OECD NEA/NSC/DOC(2004),” 2004. View at Google Scholar
  3. “ANSYS CFX User Manual,” ANSYS-CFX-10, 2006.
  4. F. Menter, “CFD Best Practice Guidelines for CFD Code Validation for Reactor Safety Applications,” ECORA FIKS-CT-2001-00154, 2002.
  5. R. J. Hertlein, K. Umminger, S. Kliem, H.-M. Prasser, T. Höhne, and F.-P. Weiß, “Experimental and numerical investigation of boron dilution transients in pressurized water reactors,” Nuclear Technology, vol. 141, no. 1, pp. 88–107, 2003. View at Google Scholar