Flaw growth characterization studies of irradiated pressure vessel steel by acoustic monitoring technique
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6616457
None
- Research Organization:
- Westinghouse-NES, Pittsburgh, PA
- OSTI ID:
- 6616457
- Report Number(s):
- CONF-800607-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 34
- Country of Publication:
- United States
- Language:
- English
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·
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ACOUSTIC MONITORING
ALLOYS
CARBON STEELS
CONTAINERS
CRACKS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MONITORING
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
STEEL-ASTM-A533-B
STEELS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ACOUSTIC MONITORING
ALLOYS
CARBON STEELS
CONTAINERS
CRACKS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MONITORING
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
STEEL-ASTM-A533-B
STEELS