A study was undertaken to better understand the lead-induced corrosion mechanism of nickel-based alloys used for steam generator tubing materials (alloys 600 and 690 [UNS N06600 and N06690]) in pressurized-water reactor (PWR) plants. Electrochemical measurements (corrosion potential and polarization measurements) and constant extension rate tests (CERT) of tubing materials were performed in lead-contaminated environments. Results of electrochemical measurements showed lead did not raise the corrosion potential but did increase the anodic polarization current in the passivity region, which indicated degradation of the passive oxide film. CERT results showed alloy 690 had better corrosion resistance than alloy 600, which was in good agreement with the lower intensity of the anodic current. The mechanism of lead-induced corrosion was proposed as disruption of the oxide film of the alloys as a result of the incorporation of lead.

Subject
Acids, Water, Materials, Corrosion resistant alloys, Nickel based alloys, Tubes, Aqueous environments, Lead, Acidity, Tubing, Anodic current, Alloys, Corrosion potential
Keywords:
alloy 600, alloy 690, intergranular stress corrosion cracking, lead-induced corrosion, nickel, pressurized water reactor, steam generator, transgranular stress corrosion cracking, tubing
NACE International
1998
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