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

Kaliatka, Algirdas; Uspuras, Eugenijus; Rimkevicius, Sigitas

doi:https://doi.org/10.1155/2007/52850

Science and Technology of Nuclear Installations

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Research Article | Open Access

Volume 2007 | Article ID 052850 | https://doi.org/10.1155/2007/52850

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

Algirdas Kaliatka,¹Eugenijus Uspuras,¹and Sigitas Rimkevicius¹

Academic Editor: Won-Pil Baek

Received24 Apr 2007

Accepted22 Nov 2007

Published31 Jan 2008

Abstract

Ignalina NPP is equipped with channel-type boiling-water graphite-moderated reactor RBMK-1500. Results of the level-1 probabilistic safety assessment of the Ignalina NPP have shown that in topography of the risk, the transients with failure of long-term core cooling other than LOCA are the main contributors to the core damage frequency. The total loss of off-site power with a failure to start any diesel generator, that is station blackout, is the event which could lead to the loss of long-term core cooling. Such accident could lead to multiple ruptures of fuel channels with severe consequences and should be analyzed in order to estimate the timing of the key events and the possibilities for accident management. This paper presents the results of the analysis of station blackout at Ignalina NPP. Analysis was performed using thermal-hydraulic state-of-the-art RELAP5/MOD3.2 code. The response of reactor cooling system and the processes in the reactor cavity and its venting system in case of a few fuel-channel ruptures due to overheating were demonstrated. The possible measures for prevention of the development of this beyond design basis accident (BDBA) to a severe accident are discussed.

References

K. Almenas, A. Kaliatka, and E. Uspuras, Ignalina RBMK-1500. A Source Book. Extended and Updated Version, Lithuanian Energy Institute, Kaunas, Lithuania, 1998.
View at: Google Scholar
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 Site | Google Scholar
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.
View at: Google Scholar
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 Site | Google Scholar
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.
View at: Google Scholar
“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.
View at: Google Scholar

Copyright

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.

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