Program to develop acoustic emission--flaw relationship for inservice monitoring of nuclear pressure vessels. Progress report, October 1, 1977--January 1, 1978
This program is directed to providing an experimental evaluation of detecting and analyzing flaw growth in reactor pressure boundaries through continuous monitoring for acoustic emission (AE). The investigation is currently limited to A533B, Class 1 material. Program primary objectives are: develop criteria for distinguishing significant flaws from innocuous sources; develop an AE-flaw damage model to serve as a basis for relating inservice AE to pressure vessel integrity. This report covers program work period October 1, 1977 to January 1, 1978. A room temperature fracture test was performed on a one-inch thick by six-inch wide single-edge notch (SEN) specimen. The results were similar to AE-fracture test data obtained on 2T-CT laboratory specimens in that the majority of AE occurred during crack propagation.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-06-1830
- OSTI ID:
- 6742537
- Report Number(s):
- BNWL-2232-4; NUREG/CR-0124
- Country of Publication:
- United States
- Language:
- English
Similar Records
Program to develop acoustic emission-flaw relationship for inservice monitoring of nuclear pressure vessels. Annual report, July 1, 1976 - October 1, 1977
Program to develop acoustic emission-flow relationship for inservice monitoring of nuclear pressure vessels. Progress report, February 1 - July 1, 1977. [BWR; PWR]
Related Subjects
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACOUSTIC EMISSION TESTING
ACOUSTIC MONITORING
ACOUSTIC TESTING
ALLOYS
BWR TYPE REACTORS
CARBON STEELS
CONTAINERS
COOLING SYSTEMS
DEFECTS
FRACTURE PROPERTIES
IN-SERVICE INSPECTION
INSPECTION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICAL PROPERTIES
MONITORING
NONDESTRUCTIVE TESTING
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH PROGRAMS
STEEL-ASTM-A533-B
STEELS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS