Substantiation of recommendations for ensuring the design service life of heat-transfer tubes used in a PGV-1000MKP steam generator

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 equi...

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Bibliographic Details
Published inThermal engineering Vol. 58; no. 3; pp. 190 - 201
Main Authors Popadchuk, V. S., Trunov, N. B., Brykov, S. I., Zhukov, R. Yu, Tupikov, R. A., Seleznev, A. V., Popkov, R. I., Metal’nikov, M. S., Styazhkin, P. S., Karzov, G. P., Suvorov, S. A.
Format Journal Article
LanguageEnglish
Published Dordrecht SP MAIK Nauka/Interperiodica 2011
Springer
Subjects
Engineering
Engineering Thermodynamics
Heat and Mass Transfer
Nuclear Power Station
Steam Generator
Coolant Circuit
Tube Bundle
Shutdown Mode
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Summary: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.
ISSN:0040-6015
1555-6301
DOI:10.1134/S0040601511030104