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 315

N in ; N res

a / S , 100%

9.31 Number of defects in HETs of the 2PG-1 steam generator:
1) prior to SPM-96; 2) after plugging during SPM-96, 97; 3) after
plugging during SPM-98.

( a / s )·100%

Operating time, years
a)

￿ ￿ ￿ ￿ ￿

2 c , mm

b)

9.32 Kinetics of propagation of surface cracks in relation to the
initial size at a safety factor of 10 (a) and dependence of through-
wall crack growth on the number of cycles N (b).