Specific Features of Corrosion Damage to Heat-Transfer Tubes of Steam Generators Used at Nuclear Power Stations Equipped with VVER-1000 Reactors

摘要

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 metal-lographic 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.