Science and Technology of Nuclear Installations
Volume 2007 (2007), Article ID 52850, 9 pages
doi:10.1155/2007/52850
Research Article

Relap5 Analysis of Processes in Reactor Cooling Circuit and Reactor Cavity in Case of Station Blackout in RBMK-1500

Algirdas Kaliatka, Eugenijus Uspuras, and Sigitas Rimkevicius

Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos street 3, Kaunas 44403, Lithuania

Received 24 April 2007; Accepted 22 November 2007

Academic Editor: Won-Pil Baek

Copyright © 2007 Algirdas Kaliatka 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. K. Almenas, A. Kaliatka, and E. Uspuras, Ignalina RBMK-1500. A Source Book. Extended and Updated Version, Lithuanian Energy Institute, Kaunas, Lithuania, 1998.
  2. E. Uspuras, A. Kaliatka, and V. Vileiniskis, “Development of accident management measures for RBMK-1500 in the case of loss of long-term core cooling,” Nuclear Engineering and Design, vol. 236, no. 1, pp. 47–56, 2006. View at Publisher · View at Google Scholar
  3. O. Yu. Novoselsky and V. N. Filinov, “Computational assessment of RBMK pressure tube rupture at accident heating,” in International Exchange Forum on Analytical Methods and Computational Tools for NPP Safety Assessment, Obninsk, Russia, 1996.
  4. B. Cesna, S. Rimkevicius, E. Urbonavicius, and E. Babilas, “Reactor cavity and ALS thermal-hydraulic evaluation in the case of fuel channels ruptures at Ignalina NPP,” Nuclear Engineering and Design, vol. 232, no. 1, pp. 57–73, 2004. View at Publisher · View at Google Scholar
  5. S. Rimkevicius, E. Urbonavicius, and B. Cesna, “Safety margins of RBMK-1500 accident localisation system at ignalina NPP,” in Safety Margins of Operating Reactors. Analysis of uncertainties and implications for decision making. International Atomic Energy Agency. IAEA-TECDOC-1332, pp. 95–106, Vienna, Austria, January 2003.
  6. “The analysis of steam-gas mixture release from the reactor cavity of RBMK-1500 reactor for determination of the boundaries. phase 4, results of the analysis,” Tech. Rep. 74.069, NIKIET, Moscow, Russia, 2000.