Dg. Briceno et al., STRESS-CORROSION CRACKING SUSCEPTIBILITY OF STEAM-GENERATOR TUBE MATERIALS IN AVT (ALL VOLATILE TREATMENT) CHEMISTRY CONTAMINATED WITH LEAD, Nuclear Engineering and Design, 165(1-2), 1996, pp. 161-169
Alloy 600 steam generator tubing has shown a high susceptibility to st
ress corrosion degradation at the operation conditions of pressurized
water reactors. Several contaminants, such as lead, have been postulat
ed as being responsible for producing the secondary side stress corros
ion cracking that has occurred mainly at the location where these cont
aminants can concentrate. An extensive experimental work has been carr
ied out in order to better understand the effects of lead on the stres
s corrosion cracking susceptibility of steam generator tube materials,
namely Alloys 600, 690 and 800. This paper presents the experimental
work conducted with a view to determining the influence of lead oxide
concentration in AVT (all volatile treatment) conditions on the stress
corrosion resistance of nickel alloys used in the fabrication of stea
m generator tubing.