Abstract
The present paper reports the results of the preliminary design estimate of the behavior of the core melt in vessels of reactors of the VVER-600 and VVER-1300 types (a standard optimized and informative nuclear power unit based on VVER technology—VVER TOI) in the case of beyond-design-basis severe accidents. The basic processes determining the state of the core melt in the reactor vessel are analyzed. The concept of molten core confinement within the vessel based on the idea of outside cooling is discussed. Basic assumptions and models, as well as the results of calculation of the interaction between molten materials of the core and the wall of the reactor vessel performed by means of the SOCRAT severe accident code, are presented and discussed. On the basis of the data obtained, the requirements on the operation of the safety systems are determined, upon the fulfillment of which there will appear potential prerequisites for implementing the concept of the confinement of the core melt within the reactor in cases of severe accidents at nuclear power plants equipped with VVER reactors.
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Original Russian Text © Yu.A. Zvonaryov, M.A. Budaev, A.M. Volchek, V.A. Gorbaev, V.N. Zagryazkin, N.P. Kiselyov, V.L. Kobzar’, A.V. Konobeev, D.F. Tsurikov, 2012, published in VANT. Fizika yadernykh reaktorov, 2012, No. 2, pp. 93–107.
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Zvonaryov, Y.A., Budaev, M.A., Volchek, A.M. et al. Design analysis of the molten core confinement within the reactor vessel in the case of severe accidents at nuclear power plants equipped with a reactor of the VVER type. Phys. Atom. Nuclei 76, 1688–1699 (2013). https://doi.org/10.1134/S106377881314010X
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DOI: https://doi.org/10.1134/S106377881314010X