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Review of secondary side tube degradation processes in PWR steam generators

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6839795

The NiCrFe Alloy 600 is the pressurized water reactor (PWR) steam generator tube material used in essentially all US PWRs, in most foreign PWRs, and thus is the tube material with the greatest service experience. Numerous laboratory investigations and service experience have demonstrated that Alloy 600 has good corrosion resistance in the steam generator secondary side environments expected under normal operating conditions. Experience in the laboratory and in the field, however, has demonstrated that even low levels of contaminants may concentrate in tubesheet crevices, in deep tubesheet sludge piles, and in tube support structure crevices to levels that promote several types of corrosion (pitting, intergranular attack, stress corrosion cracking, wastage) of the tube material. Low levels of contaminants, such as chlorides, sulfates, and oxygen, in the secondary system result from condenser cooling water and air in-leakage and from impurity releases from condensate polishers. This discussion reviews the corrosion-related secondary side tube degradation processes that have affected steam generator tubes in recent years and also mechanical tube damage resulting from fatigue and wear of the tube material.

Research Organization:
Combustion Engineering, Inc., Chicago, IL
OSTI ID:
6839795
Report Number(s):
CONF-861102-
Journal Information:
Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 53; ISSN TANSA
Country of Publication:
United States
Language:
English