Published October 1984
| Version v1
Report
Restricted
Summary of detection, location, and characterization capabilities of AE for continuous monitoring of cracks in reactors
Description
The objective of the program is to develop acoustic emission (AE) methods for continuous monitoring of reactor pressure boundaries to detect and evaluate crack growth. The approach involves three phases: develop relationships to identify crack growth AE signals and to use identified crack growth AE data to estimate flaw severity; evaluate and refine AE/flaw relationships through fatigue testing a heavy section vessel under simulated reactor conditions; and demonstrate continuous AE monitoring on a nuclear power reactor system
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE85005294.
Files
Additional details
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- PNL-SA--12548
Conference
- Title
- 12. water reactor safety research information meeting.
- Dates
- 23-26 Oct 1984.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16064726
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACOUSTIC EMISSION TESTING; BWR TYPE REACTORS; CRACK PROPAGATION; CRACKS; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR MATERIALS; STEEL-MNNIMO
- Descriptors DEC
- ACOUSTIC TESTING; ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; LOW ALLOY STEELS; MANGANESE ALLOYS; MATERIALS; MATERIALS TESTING; MOLYBDENUM ADDITIONS; NICKEL ADDITIONS; NONDESTRUCTIVE TESTING; POWER REACTORS; REACTORS; STEELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8410142--78.