Evaluation and technologic improvement of an enhanced imaging system
Technical Report
·
OSTI ID:6878984
- General Electric Co., San Jose, CA (USA). Nuclear Energy Div.
Feature-based systems that combine imaging and signal analysis capabilities may be useful for nondestructive evaluation (NDE) of plant components. This report describes the metallurgical evaluation conducted to verify the performance of a feature-based system to discriminate intergranular stress corrosion cracking (IGSCC) from benign geometrical reflectors. The ultrasonic examination results were also evaluated by examination personnel trained in intergranular stress corrosion cracking (IGSCC) detection techniques. The welds were examined prior to their removal from the recirculation and Residual-Heat-Removal (RHR) piping systems of the Peach Bottom Atomic Power Plant, as described in the Phase 2 Interim Report issued in June 1989. In this phase of the program, a metallurgical evaluation was performed on piping system welds that were examined ultrasonically using a feature-based system for analysis. The feature-based system correctly identified crack, but incorrectly identified other features, e.g., root geometry and metallurgical interfaces, as cracks. While the results of the analysis by the feature-based system were not identical to the results of analysis by trained personnel, the overall performance of the feature-based system was comparable to that of the trained personnel. Based on the results of this program, the feature-based system may be useful as a supplementary method of identifying IGSCC indications. When used in conjunction with existing methods and techniques, it could improve the accuracy of IGSCC identification.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (USA); General Electric Co., San Jose, CA (USA). Nuclear Energy Div.
- Sponsoring Organization:
- EPRI
- OSTI ID:
- 6878984
- Report Number(s):
- EPRI-NP-6948
- 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
CHEMICAL REACTIONS
CORROSION
CRACK PROPAGATION
CRACKS
EVALUATION
IMAGE PROCESSING
JOINTS
MATERIALS TESTING
NONDESTRUCTIVE TESTING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PROCESSING
RELIABILITY
STRESS CORROSION
TESTING
THERMAL POWER PLANTS
WELDED JOINTS
220200 -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420500* -- Engineering-- Materials Testing
CHEMICAL REACTIONS
CORROSION
CRACK PROPAGATION
CRACKS
EVALUATION
IMAGE PROCESSING
JOINTS
MATERIALS TESTING
NONDESTRUCTIVE TESTING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PROCESSING
RELIABILITY
STRESS CORROSION
TESTING
THERMAL POWER PLANTS
WELDED JOINTS