The results of a computational analysis of the behavior of melt in the facility used to localize melt for VVER-1200 (AES-2006 design), which were obtained using the GEFEST-ULR code, are presented. The main parameters of the melt are determined: the time variation of the component composition, the temperature and density of the oxide and metallic components and their relative arrangement. Using the KORSAR/GP thermohydraulic code, the minimum margin to crisis of heat transfer at the outer surface of the wall of the melt localization facility is analyzed. It is confirmed that heat transfer from the outer surface of the wall with normal operation of the cooling loop is reliable.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
I. V. Kukhtevich,V. V. Bezlepkin,V. S. Granovskii, et al., “Concept of localization of the corium melt of the Tian Wan nuclear power plant at the extra-vessel stage of an unanticipated accident at a nuclear power plant with VVER-1000,” in: Questions Concerning the Safety of Nuclear Power Plants with VVER, St. Petersburg, September 12–14, 2000.
I. V. Kukhtevich, V. V. Bezlepkin, V. S. Granovskii, et al., “Concept of localization of the corium melt at the extravessel stage of an unanticipated accident at a nuclear power plant with VVER-1000,” Teploenerg., No. 9, 35–42 (2001).
A. S. Sidorov, A. B. Nedorezov, M. F. Rogov, et al., “Facility for localizing melt of the Tian Wan nuclear power plant with VVER-1000,” ibid., pp.43–49.
Yu. A. Zvonarev, D. F. Tsurikov, V. L. Kobzar, et at., “Computational analysis of the functional effectiveness of the melt-localization facility for VVER-1200,” Vopr. At. Nauki Tekhn. Ser. Fiz. Yad. Reakt., No. 1, 17–22 (2010).
V. V. Bezlepkin, V. G. Sidorov, A. V. Lukin, et al., “Development of computer codes for modeling serious accidents in nuclear power plants,” Teploenerg., No. 2, 5–11 (2004).
Software Certificate for KORSAR/GP No. 263 of September 23, 2009, Federal Oversight Agency of Russia for Nuclear and Radiological Safety, Moscow.
A. A. Sulatskii, O. D. Chernyi, V. K. Efimov, et al., “Critical heat transfer on the outer surface of a VVER vessel,” Teploenerg., No. 11, 35–39 (1998).
T. Theofanous and S. Syri, “The coolability limits of a lower reactor pressure vessel head,” in: NURETH-7, New York, September 10–15, 1995, NUREGCP-0142, Vol. 1, pp. 627–647.
Yu. V. Yudov, S. N. Volkova, and Yu. A. Migrov, “Closure relations for the thermohydraulic model used in the KORSAR code,” Teploenerg., No. 11, 22–29 (2002).
Author information
Authors and Affiliations
Additional information
Translated from Atomnaya Énergiya, Vol. 108, No. 6, pp. 327–333, June, 2010.
Rights and permissions
About this article
Cite this article
Bezlepkin, V.V., Sidorov, V.G., Astafieva, V.O. et al. Modeling processes in the melt localization facility for aes-2006 with vver-1200 during an unanticipated accident. At Energy 108, 395–404 (2010). https://doi.org/10.1007/s10512-010-9308-x
Received:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10512-010-9308-x