A unified description of radiation embrittlement and annealing in pressure vessel steels
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6648259
None
- Research Organization:
- Westinghouse Electric Corporation, Research and Development Center, 1310 Beulah Road, Pittsburgh, PA 15235
- OSTI ID:
- 6648259
- Report Number(s):
- CONF-840614-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 46
- 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
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
ANNEALING
CONTAINERS
CRYSTAL STRUCTURE
DUCTILE-BRITTLE TRANSITIONS
EMBRITTLEMENT
HEAT TREATMENTS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
MICROSTRUCTURE
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR COMPONENTS
STEELS
YIELD STRENGTH
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
ANNEALING
CONTAINERS
CRYSTAL STRUCTURE
DUCTILE-BRITTLE TRANSITIONS
EMBRITTLEMENT
HEAT TREATMENTS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
MICROSTRUCTURE
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR COMPONENTS
STEELS
YIELD STRENGTH