Using probabilistic methods for solving the problem of ensuring leak tightness of heat exchanger tubes of nuclear power plant steam generators - Probabilistic Safety Assessment for Optimum Nuclear Power Plant Life Management (PLiM) - page 284

9.9 Cracking of a heat exchange tube (61-1, second semicircle)
in the zone of contact with spacing grid 2, ×100: 1) outer surface
of the heat exchange tube, 2) the inner surface.
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9.10 Corrosion defects on the outer surface of the tube section
under spacing grid, ×10 0.
Accumulation of corrosion products from the condensate feed circuit in
combination with products of suction, as well as short-term violations of
water chemistry, were the cause of damage such as cracks.
9.2 Application of the Monte Carlo method to the
problem of ensuring the integrity of HETs of VSG
This analysis was carried out in Ref. 29. Growth of stress corrosion
cracks in steam generator tubes is estimated using statistical approaches
and Monte Carlo simulation method. Statistical parameters that define the