Thermal-hydraulic and mechanical analyses for near-term fusion reactor blanket designs
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5173224
None
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 5173224
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 27
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700204* -- Fusion Power Plant Technology-- Cooling Systems
ALLOYS
BREEDING BLANKETS
CHROMIUM ALLOYS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
PHYSICAL PROPERTIES
REACTOR COMPONENTS
STAINLESS STEELS
STEELS
STRESSES
THERMAL STRESSES
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTORS
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700204* -- Fusion Power Plant Technology-- Cooling Systems
ALLOYS
BREEDING BLANKETS
CHROMIUM ALLOYS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
PHYSICAL PROPERTIES
REACTOR COMPONENTS
STAINLESS STEELS
STEELS
STRESSES
THERMAL STRESSES
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTORS