Optimizing pre-service inspection data
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6772144
The phenomenon of intergranular stress corrosion cracking (IGSCC) in nuclear power plant piping systems has been the single biggest factor in an evolution that has changed and continues to change in-service inspection practices and philosophy throughout the industry. In-service inspection has been found to deal with several distinct phases of the problem. At the onset, existing technology was demonstrated to be unable to detect IGSCC adequately. This inability to detect IGSCC was soon overcome. However, it immediately pointed out the difficulties associated with the discrimination between IGSCC and other harmless metallurgical conditions. On the heels of detection and discrimination came problems associated with determining crack size and the monitoring of overlayed flaws. A wealth of information has been written on all phases of IGSCC; however, one particular aspect has as of yet seen little attention. With an increasing number of plants choosing to replace flawed pipe, the pre-service inspection of the replaced piping demands increased attention. The lessons learned through inspection for IGSCC need again to be applied to the replacement piping. Through increased attention at installation, many of the difficulties associated with proper inservice inspection may be reduced or eliminated, thereby realizing an economy in outage scheduling, personnel exposure, and, overall, a more reliable in-service examination.
- Research Organization:
- Yankee Atomic Electric Co., Framingham, MA
- OSTI ID:
- 6772144
- Report Number(s):
- CONF-860610-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
42 ENGINEERING
420500 -- Engineering-- Materials Testing
BWR TYPE REACTORS
CHEMICAL REACTIONS
CONSTRUCTION
COOLING SYSTEMS
CORROSION
CRACKS
DEFECTS
DESIGN
ENERGY SYSTEMS
FABRICATION
INSPECTION
INSTALLATION
INTERGRANULAR CORROSION
PERFORMANCE TESTING
PIPES
PRIMARY COOLANT CIRCUITS
RADIATION PROTECTION
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RELIABILITY
REPAIR
STRESS CORROSION
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
42 ENGINEERING
420500 -- Engineering-- Materials Testing
BWR TYPE REACTORS
CHEMICAL REACTIONS
CONSTRUCTION
COOLING SYSTEMS
CORROSION
CRACKS
DEFECTS
DESIGN
ENERGY SYSTEMS
FABRICATION
INSPECTION
INSTALLATION
INTERGRANULAR CORROSION
PERFORMANCE TESTING
PIPES
PRIMARY COOLANT CIRCUITS
RADIATION PROTECTION
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RELIABILITY
REPAIR
STRESS CORROSION
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS