Chamber design for the LIBRA light ion beam fusion reactor
Conference
·
· Fusion Technol.; (United States)
OSTI ID:6277830
Scoping analysis was performed for LIBRA to determine the blanket design options that satisfy the tritium breeding and wall protection requirements. The blanket is made of banks of INPORT tubes of porous SiC and Li/sub 17/Pb/sub 83/ flowing in them. The reference design utilizes a 1.35 m thick blanket region backed by a 0.5 m thick HT-9 reflector. The lithium in the blanket and reflector is enriched to 90% /sup 6/Li. This design leads to the shortest possible beam propagation channel. The TBR is 1.5 and the end-of-life dpa in the chamber wall is 200 dpa. In this paper the authors describe the design and configuration of the chamber as well as the tritium fueling and the response to the target explosion.
- Research Organization:
- Univ. of Wisconsin, Madison, WI (US)
- OSTI ID:
- 6277830
- Report Number(s):
- CONF-881031-
- Conference Information:
- Journal Name: Fusion Technol.; (United States) Journal Volume: 15:2
- 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
ALKALI METALS
BEAMS
BREEDING BLANKETS
CARBIDES
CARBON COMPOUNDS
CHARGED PARTICLES
DESIGN
ELEMENTS
FIRST WALL
ION BEAMS
IONS
IRRADIATION REACTORS
LEAD
LIGHT IONS
LITHIUM
MATERIALS TESTING
METALS
RADIATION PROTECTION
REACTOR COMPONENTS
REACTORS
SAFETY
SILICON CARBIDES
SILICON COMPOUNDS
TARGETS
TESTING
THERMONUCLEAR REACTOR WALLS
TRITIUM PRODUCTION REACTORS
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ALKALI METALS
BEAMS
BREEDING BLANKETS
CARBIDES
CARBON COMPOUNDS
CHARGED PARTICLES
DESIGN
ELEMENTS
FIRST WALL
ION BEAMS
IONS
IRRADIATION REACTORS
LEAD
LIGHT IONS
LITHIUM
MATERIALS TESTING
METALS
RADIATION PROTECTION
REACTOR COMPONENTS
REACTORS
SAFETY
SILICON CARBIDES
SILICON COMPOUNDS
TARGETS
TESTING
THERMONUCLEAR REACTOR WALLS
TRITIUM PRODUCTION REACTORS