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Development and application of an information-analytic system on the problem of flow accelerated corrosion of pipeline elements in the secondary coolant circuit of VVER-440-based power units at the Novovoronezh nuclear power plant

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An Erratum to this article was published on 23 June 2016

Abstract

Specific features relating to development of the information-analytical system on the problem of flow-accelerated corrosion of pipeline elements in the secondary coolant circuit of the VVER-440-based power units at the Novovoronezh nuclear power plant are considered. The results from a statistical analysis of data on the quantity, location, and operating conditions of the elements and preinserted segments of pipelines used in the condensate-feedwater and wet steam paths are presented. The principles of preparing and using the information-analytical system for determining the lifetime to reaching inadmissible wall thinning in elements of pipelines used in the secondary coolant circuit of the VVER-440-based power units at the Novovoronezh NPP are considered.

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Correspondence to G. V. Tomarov.

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Original Russian Text © G.V. Tomarov, V.P. Povarov, A.A. Shipkov, A.F. Gromov, A.N. Kiselev, S.V. Shepelev, A.V. Galanin, 2015, published in Teploenergetika.

An erratum to this article is available at http://dx.doi.org/10.1134/S0040601516070090.

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Tomarov, G.V., Povarov, V.P., Shipkov, A.A. et al. Development and application of an information-analytic system on the problem of flow accelerated corrosion of pipeline elements in the secondary coolant circuit of VVER-440-based power units at the Novovoronezh nuclear power plant. Therm. Eng. 62, 138–145 (2015). https://doi.org/10.1134/S0040601515020111

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  • DOI: https://doi.org/10.1134/S0040601515020111

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