Acoustic emission/flaw relationship for in-service monitoring of nuclear pressure vessels: Progress report, April 1986-September 1986

Technical Report · Wed Dec 31 23:00:00 EST 1986

OSTI ID:6839852

Hutton, P H

This report discusses technical progress for the period April 1986 to September 1986 for the NRC-sponsored research program concerned with ''Acoustic Emission/Flaw Relationships for Inservice Monitoring of Nuclear Reactor Pressure Boundaries.'' Included in the discussion are the topics of AE monitoring of primary piping during reactor operation, substantiation of the AE signal identification method, development of AE/IGSCC relationships, and progress in establishing an ASTM AE standard and an ASME code appendix for on-line AE monitoring.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering Safety
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6839852
• Report Number(s): NUREG/CR-4300-Vol.3-No.2; PNL-5511-Vol.3-No.2; ON: TI87005635
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACOUSTIC EMISSION TESTING
ACOUSTIC TESTING
BWR TYPE REACTORS
COOLING SYSTEMS
DEFECTS
ENERGY SYSTEMS
IN-SERVICE INSPECTION
INSPECTION
MATERIALS TESTING
NONDESTRUCTIVE TESTING
PIPES
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH PROGRAMS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS