Acoustic emission/flaw relationship for in-service monitoring of nuclear pressure vessels: Progress report, October 1986-March 1987

Technical Report · Mon Jun 01 00:00:00 EDT 1987

OSTI ID:6305695

Hutton, P H; Friesel, M A

This report discusses technical progress for the period October 1986 to March 1987 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, development of AE/IGSCC relationships, evaluation of the effects of crack growth rate on detection of the associated AE, validation of the AE signal identification, and progress in developing an ASME Section XI Code appendix for continuous AE monitoring of pressure boundary components.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6305695
• Report Number(s): NUREG/CR-4300-Vol.4-No.1; PNL-5511-Vol.4-No.1; ON: TI87011711
• 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
CONTAINERS
CRACK PROPAGATION
DATA
EXPERIMENTAL DATA
FRACTURE MECHANICS
IN-SERVICE INSPECTION
INFORMATION
INSPECTION
MATERIALS TESTING
MECHANICS
NONDESTRUCTIVE TESTING
NUMERICAL DATA
OPERATION
PIPES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR OPERATION
REACTORS
REPORTING REQUIREMENTS
RESEARCH PROGRAMS
STANDARDS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS