Thermal and structural analyses of a helium-cooled blanket design for a tokamak reactor
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5233077
None
- Research Organization:
- Fusion Power Systems Dept., Pittsburgh, PA
- OSTI ID:
- 5233077
- Report Number(s):
- CONF-791103-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 33
- 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
BREEDING BLANKETS
COOLANTS
CRYOGENIC FLUIDS
DESIGN
ELEMENTS
FLUIDS
HELIUM
MECHANICAL STRUCTURES
NONMETALS
PHYSICAL PROPERTIES
POWER DENSITY
RARE GASES
REACTOR COMPONENTS
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
WALL LOADING
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700204 -- Fusion Power Plant Technology-- Cooling Systems
BREEDING BLANKETS
COOLANTS
CRYOGENIC FLUIDS
DESIGN
ELEMENTS
FLUIDS
HELIUM
MECHANICAL STRUCTURES
NONMETALS
PHYSICAL PROPERTIES
POWER DENSITY
RARE GASES
REACTOR COMPONENTS
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
WALL LOADING