Acoustic emission/flaw relationship for in-service monitoring of nuclear pressure vessels. Quarterly report, April-September 1984. Volumes 3, 4
Technical progress toward continuous acoustic emission monitoring of nuclear reactor pressure boundaries for flaw detection is described for this period. A draft report of ZB-1 vessel test results was completed. Growth of machined flaws was detected by AE during both 65/sup 0/C and 285/sup 0/C testing. A key result was clear detection of a natural crack in a fabrication weld by AE. Crack growth rates estimated from AE data compared well with measured crack growth rates for the machined defects. In service hydro test monitoring gave mixed results. Questionable vessel integrity as denoted by continued AE at pressure hold is readily detectable. With low overpressure (1.15 x operating pressure), flaws as deep as 70% through-wall did not produce significant AE. With higher overpressure (1.4 x operating pressure), flaws produced identifying AE. An engineering prototype AE monitor system has been completed for use in operational monitoring at Watts Bar Unit 1 reactor. A modified approach to crack growth AE signal identification is producing about 95% correct determinations on recorded waveforms from the ZB-1 vessel test. A report on results from AE monitoring hot functional testing at Watts Bar Unit 1 has been published.
- Research Organization:
- Pacific Northwest Labs., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6123462
- Report Number(s):
- NUREG/CR-3825-Vols.3-4; PNL-5125-Vols.3-4; ON: TI85009374
- Country of Publication:
- United States
- Language:
- English
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Current capabilities for continuous AE monitoring to detect flaws in reactor pressure boundaries
Acoustic emission/flaw relationship for in-service monitoring of nuclear pressure vessels. Quarterly report, October 1983-March 1984. Volumes 1 and 2
Related Subjects
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACOUSTIC EMISSION TESTING
ACOUSTIC TESTING
CHEMICAL REACTIONS
CONTAINERS
CORROSION
CRACK PROPAGATION
DEFECTS
ENRICHED URANIUM REACTORS
MATERIALS TESTING
NONDESTRUCTIVE TESTING
POWER REACTORS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
RESEARCH PROGRAMS
STRESS CORROSION
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WATTS BAR-1 REACTOR