Observation of denting and other deterioration in the Surry steam generator
Conference
·
OSTI ID:5199148
A Westinghouse type 51 steam generator has been the subject of extensive nondestructive and destructive examination. The Steam Generator Group Project acquired the A generator removed from the Surry 2 nuclear station after less than six years of service. At the time of replacement, this generator had approx.22% of its tubes plugged due to indicated defects or as a preventive measure. The generator had known wastage, stress corrosion cracking and denting damage to tubes when removed from service. Subsequent investigation has characterized severe support plate degradation, denting in the tube sheet, pitting in the sludge pile and potential IGA at the top of the tube sheet. The extent and characterization of this damage are discussed in the paper.
- Research Organization:
- Pacific Northwest Labs., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5199148
- Report Number(s):
- PNL-SA-13273; CONF-850792-1; ON: TI85017921
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BOILERS
CORROSION DENTING
DEFORMATION
ENRICHED URANIUM REACTORS
POWER REACTORS
PWR TYPE REACTORS
REACTORS
STEAM GENERATORS
SURRY-2 REACTOR
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BOILERS
CORROSION DENTING
DEFORMATION
ENRICHED URANIUM REACTORS
POWER REACTORS
PWR TYPE REACTORS
REACTORS
STEAM GENERATORS
SURRY-2 REACTOR
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS