Corrosion of steam generator tubing in operating pressurized water reactors
Conference
·
OSTI ID:4104564
- ed.
Corrosion of steam generator tubing has been observed in all but three PWR's that have been in operation for more than one year. The history of this experience with both stainless steel and Inconel-600 tubing is reviewed. Both intergranular stress corrosion cracking and localized, transgranular wastage have been observed with Inconel-600 tubing. The wastage can be attributed to a localized concentration, or ''hideout'' of phosphates in limited flow areas. A model is proposed for this wastage phenomenon which is consistent with operating experience. 33 references. (auth)
- Research Organization:
- Atomic Energy Commission, Washington, DC
- NSA Number:
- NSA-33-013945
- OSTI ID:
- 4104564
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
*INCONEL 600-- STRESS CORROSION
*PWR TYPE REACTORS-- STEAM GENERATORS
*STAINLESS STEELS-- STRESS CORROSION
*STEAM GENERATORS-- TUBES
*TUBES-- STRESS CORROSION
210200* --Nuclear Power Plants--Power Reactors
Non- Breeding
Light-Water Moderated
Non-Boiling Water Cooled
N50210 --Metals
Ceramics
& Other Materials--Metals & Alloys--Corrosion & Erosion & Surface Phenomena
N77200* --Reactors--Power Reactors
Non-breeding
Light- water Moderated
Non-boiling Water-cooled
PERFORMANCE
PH VALUE
REACTOR OPERATION
WATER CHEMISTRY
*PWR TYPE REACTORS-- STEAM GENERATORS
*STAINLESS STEELS-- STRESS CORROSION
*STEAM GENERATORS-- TUBES
*TUBES-- STRESS CORROSION
210200* --Nuclear Power Plants--Power Reactors
Non- Breeding
Light-Water Moderated
Non-Boiling Water Cooled
N50210 --Metals
Ceramics
& Other Materials--Metals & Alloys--Corrosion & Erosion & Surface Phenomena
N77200* --Reactors--Power Reactors
Non-breeding
Light- water Moderated
Non-boiling Water-cooled
PERFORMANCE
PH VALUE
REACTOR OPERATION
WATER CHEMISTRY