Acoustic emission for on-line reactor monitoring: results of intermediate vessel test monitoring and reactor hot functional testing
Conference
·
OSTI ID:5565171
The objective of the acoustic emission (AE)/flaw characterization program is to provide an experimental feasibility evaluation of using the AE method on a continuous basis (during operation and during hydrotest) to detect and analyze flaw growth in reactor pressure vessels and primary piping. This effort is based on earlier results showing that AE has potential for being a valuable addition to nondestructive evaluation (NDE) methods with the added unique capability for continuous monitoring, high sensitivity and remote flaw location. Results are reported for the ZB-1 vessel test and the Watts Bar-1 hot functional test.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5565171
- Report Number(s):
- PNL-SA-11634; CONF-8310143-61; ON: DE84003259
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420500 -- Engineering-- Materials Testing
ACOUSTIC EMISSION TESTING
ACOUSTIC MONITORING
ACOUSTIC TESTING
ALLOYS
CONTAINERS
COOLING SYSTEMS
CRACKS
DEFECTS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MONITORING
NONDESTRUCTIVE TESTING
POWER REACTORS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STEEL-ASTM-A533
STEELS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WATTS BAR-1 REACTOR
220200* -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420500 -- Engineering-- Materials Testing
ACOUSTIC EMISSION TESTING
ACOUSTIC MONITORING
ACOUSTIC TESTING
ALLOYS
CONTAINERS
COOLING SYSTEMS
CRACKS
DEFECTS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MONITORING
NONDESTRUCTIVE TESTING
POWER REACTORS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STEEL-ASTM-A533
STEELS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WATTS BAR-1 REACTOR