Thermal and structural analyses of a helium-cooled blanket design for a tokamak reactor
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5233077
- Research Organization:
- Fusion Power Systems Dept., Pittsburgh, PA
- OSTI ID:
- 5233077
- Report Number(s):
- CONF-791103-; TRN: 80-013224
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 33; Conference: American Nuclear Society meeting, San Francisco, CA, USA, 12 Nov 1979
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
DESIGN
THERMODYNAMIC PROPERTIES
TOKAMAK TYPE REACTORS
COOLANTS
HELIUM
MECHANICAL STRUCTURES
WALL LOADING
CRYOGENIC FLUIDS
ELEMENTS
FLUIDS
NONMETALS
PHYSICAL PROPERTIES
POWER DENSITY
RARE GASES
REACTOR COMPONENTS
THERMONUCLEAR REACTORS
700201* - Fusion Power Plant Technology- Blanket Engineering
700204 - Fusion Power Plant Technology- Cooling Systems
BREEDING BLANKETS
DESIGN
THERMODYNAMIC PROPERTIES
TOKAMAK TYPE REACTORS
COOLANTS
HELIUM
MECHANICAL STRUCTURES
WALL LOADING
CRYOGENIC FLUIDS
ELEMENTS
FLUIDS
NONMETALS
PHYSICAL PROPERTIES
POWER DENSITY
RARE GASES
REACTOR COMPONENTS
THERMONUCLEAR REACTORS
700201* - Fusion Power Plant Technology- Blanket Engineering
700204 - Fusion Power Plant Technology- Cooling Systems