Feedwater nozzle inspection evaluation
Technical Report
·
OSTI ID:5949169
This report presents a summary of a series of investigations into ultrasonic testing (UT) of reactor pressure vessel feedwater nozzles for detection of thermal fatigue cracks. The report includes an assessment of the reliability of contemporary field UT techniques and describes the development and usage of a mock-up nozzle that is available to utilities for verification of proposed techniques. The status of ongoing development and the relationship between inspection capability and fitness-for-service determinations are also briefly described.
- Research Organization:
- Southwest Research Inst., San Antonio, TX (USA)
- OSTI ID:
- 5949169
- Report Number(s):
- EPRI-NP-2025-SY; ON: DE82900329
- 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
ACOUSTIC TESTING
BWR TYPE REACTORS
CONTAINERS
CRACKS
DEFECTS
FATIGUE
FEEDWATER
HYDROGEN COMPOUNDS
INSPECTION
MATERIALS TESTING
MECHANICAL PROPERTIES
NONDESTRUCTIVE TESTING
NOZZLES
OXYGEN COMPOUNDS
PRESSURE VESSELS
REACTORS
TESTING
THERMAL FATIGUE
ULTRASONIC TESTING
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
ACOUSTIC TESTING
BWR TYPE REACTORS
CONTAINERS
CRACKS
DEFECTS
FATIGUE
FEEDWATER
HYDROGEN COMPOUNDS
INSPECTION
MATERIALS TESTING
MECHANICAL PROPERTIES
NONDESTRUCTIVE TESTING
NOZZLES
OXYGEN COMPOUNDS
PRESSURE VESSELS
REACTORS
TESTING
THERMAL FATIGUE
ULTRASONIC TESTING
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS