Abstract
Safety and efficiency of nuclear power plants (NPP) are dependent of the technical state of heat exchanger tubes installed in steam generators (SG). The majority of Russian and Ukrainian WWER type NPP units as well as NPP in Czech Republic (Temelin) and Bulgaria (Kozloduy) are equipped by PGV-1000 type SG. These NPP units were introduced into service from 1982 to 2004. Decommissioning dates (or dates of life time prolongation) are planned from 2012 to 2034 (Balitskii et al., 2005). SG heat exchanger tubes create a barrier between the radioactive primary and secondary water circuits and are one of the most critical component in NPP due different type defects and damages initiated during inservice life (Neklyudov et al., 2006; Mytrofanov et al., 2008). The in-service defects appear along the full tube length and in the zone of the tubes mounting to collector desk. Therefore, the complex diagnostics of heat exchanger tubes based on the trustworthy results of nondestructive testing is the question of great importance (IAEA-TECDOC-981, 1997; IAEAEBP-VVER-11, 1998; IAEA-TECDOC-1400, 2004).
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