Nucleonic performance aspects of thorium fusion-fission hybrid blanket designs
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5271539
- Research Organization:
- General Atomic Co., San Diego, CA
- OSTI ID:
- 5271539
- Report Number(s):
- CONF-791103-; TRN: 80-013227
- 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
HYBRID REACTORS
HYBRID SYSTEMS
NEUTRON TRANSPORT
THORIUM CARBIDES
THORIUM CYCLE
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
FUEL CYCLE
NEUTRAL-PARTICLE TRANSPORT
RADIATION TRANSPORT
REACTOR COMPONENTS
THORIUM COMPOUNDS
700201* - Fusion Power Plant Technology- Blanket Engineering
BREEDING BLANKETS
DESIGN
HYBRID REACTORS
HYBRID SYSTEMS
NEUTRON TRANSPORT
THORIUM CARBIDES
THORIUM CYCLE
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
FUEL CYCLE
NEUTRAL-PARTICLE TRANSPORT
RADIATION TRANSPORT
REACTOR COMPONENTS
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