Abstract
We present the results obtained from tests and studies carried out on the model of tube bundles for a PGV-1000 horizontal steam generator that were conducted for experimentally substantiating the design service life of a steam generator tube bundle intended for use at new nuclear power stations equipped with a PGV-1000MKP steam generator. Measures taken to minimize the incipience and development of local corrosion damage to the heat-transfer tubes and ensure their design service life are substantiated and confirmed.
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Original Russian Text © V.S. Popadchuk, N.B. Trunov, S.I. Brykov, R.Yu. Zhukov, R.A. Tupikov, A.V. Seleznev, R.I. Popkov, M.S. Metal’nikov, P.S. Styazhkin, G.P. Karzov, S.A. Suvorov, 2011, published in Teploenergetika.
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Popadchuk, V.S., Trunov, N.B., Brykov, S.I. et al. Substantiation of recommendations for ensuring the design service life of heat-transfer tubes used in a PGV-1000MKP steam generator. Therm. Eng. 58, 190–201 (2011). https://doi.org/10.1134/S0040601511030104
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DOI: https://doi.org/10.1134/S0040601511030104