Acoustic emission/flaw relationships for inservice monitoring of LWRs
- Pacific Northwest Lab., Richland, WA (United States)
The program concerning Acoustic Emission/Flaw Relationships for Inservice Monitoring of LWRs was initiated in FY76 with the objective of validating the application of acoustic emission (AE) to monitor nuclear reactor pressure-containing components during operation to detect cracking. The program has been supported by the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. Research and development has been performed by Pacific Northwest Laboratory, operated for the Department of Energy by Battelle Memorial Institute. The program has shown the feasibility of continuous, on-line AE monitoring to detect crack growth and produced validated methods for applying the technology. Included are relationships for estimating flaw severity from AE data and field applications at Watts Bar Unit 1 Reactor, Limerick Unit 1 Reactor, and the High Flux Isotope Reactor. This report discusses the program scope and organization, the three program phases and the results obtained, standard and code activities, and instrumentation and software developed under this program.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 10106282
- Report Number(s):
- NUREG/CR--5645; PNL--7479; ON: TI92004727
- Country of Publication:
- United States
- Language:
- English
Similar Records
Acoustic emission/flaw relationship for in-service monitoring of nuclear pressure vessels: Progress report, October 1986-March 1987
Progress for on-line acoustic emission monitoring of cracks in reactor systems
Related Subjects
210100
210200
ACOUSTIC EMISSION TESTING
CALIBRATION
CRACK PROPAGATION
EVALUATION
FATIGUE
HFIR REACTOR
LEAKS
LIMERICK-1 REACTOR
MONITORING
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PRESSURE VESSELS
STRESS CORROSION
TECHNOLOGY TRANSFER
TEMPERATURE EFFECTS
TENSILE PROPERTIES
WATTS BAR-1 REACTOR