Liquid metal breeder-coolant blanket concept
Conference
·
OSTI ID:6844447
This paper discusses the results and conclusions of a self-cooled, liquid-metal design for a D-T fusion reactor, which is part of the Blanket Comparison and Selection Study (BCSS). The effort reported in this paper emphasizes the inboard blanket of a tokamak since the problem is most severe in this region. The work on a self-cooled TMR is also reported.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6844447
- Report Number(s):
- CONF-840614-39; ON: DE84006554
- 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
BREEDING BLANKETS
COMPARATIVE EVALUATIONS
COOLANTS
COOLING SYSTEMS
DESIGN
ELEMENTS
ENERGY SYSTEMS
FLUIDS
LIQUID METALS
LIQUIDS
LITHIUM
METALS
REACTOR COMPONENTS
RECOVERY
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRANSITION ELEMENTS
TRITIUM RECOVERY
VANADIUM
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ALKALI METALS
BREEDING BLANKETS
COMPARATIVE EVALUATIONS
COOLANTS
COOLING SYSTEMS
DESIGN
ELEMENTS
ENERGY SYSTEMS
FLUIDS
LIQUID METALS
LIQUIDS
LITHIUM
METALS
REACTOR COMPONENTS
RECOVERY
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRANSITION ELEMENTS
TRITIUM RECOVERY
VANADIUM