Specific features of corrosion damage to heat-transfer tubes of steam generators used at nuclear power stations equipped with VVER-1000 reactors |
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Authors: | D. S. Nemytov V. F. Tyapkov |
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Affiliation: | (1) Institute for Nuclear Power Plant Research (OAO VNIIAES), ul. Ferganskaya 25, Moscow, 109507, Russia |
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Abstract: | Specific features of corrosion damage occurring to the heat-transfer tubes of steam generators used at nuclear power stations equipped with VVER-1000 reactors are considered. The results obtained from metallographic studies of flaws found in samples cut out from steam-generator tubes are analyzed. Regularities with which flaws of steam-generator tubes are distributed over the tube bundle volume are discussed. Approaches for assessing the technical state and remaining service life of steam-generator tubes are presented. |
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