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Special features of steam–gas flow through a crack in the protective envelope of a nuclear power plant

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Experimental data on the escape of steam and liquid drops with the outflow of a steam–air mixture through a model of a crack in a concrete protective envelope are presented. The experiments are performed using cold and heated concrete assemblies. Complete condensation of the steam on the surface of a crack occurs at relatively low temperatures of the concrete assembly. As the concrete assembly is heated, drops appear in the gas flow at the exit.

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Translated from Atomnaya Énergiya, Vol. 97, No. 5, pp. 333–338, November, 2004.

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Kalyakin, S.G., Tsyganok, A.A., Taranov, G.S. et al. Special features of steam–gas flow through a crack in the protective envelope of a nuclear power plant. At Energy 97, 744–749 (2004). https://doi.org/10.1007/s10512-004-0002-8

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  • DOI: https://doi.org/10.1007/s10512-004-0002-8

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