Thermal analysis of lead-lithium-cooled blankets for fusion reactors
Two examples of alternate concepts for fusion reactors are the Compact Reversed-Field Pinch Reactor and the Advanced Tokamak Reactor based on the Spherical Torus. Both are compact reactors that have high-power-density cooling requirements for key fusion-power-core components. Both reactors have blankets cooled by Pb/sub 83/Li/sub 17/ eutectic and other components that are cooled by water. Thus, a dual-media steam power cycle must be used. Thermal/hydraulic analyses were developed for the design of the fusion-power-core components. A procedure was developed to optimize the design with respect to net cycle efficiency, subject to design constraints related to critical heat flux, peak temperatures, corrosion, and thermal stress. Details of the calculation procedures and results for the blanket designs for both conceptual reactors are given.
- OSTI ID:
- 5825011
- Report Number(s):
- CONF-861211-
- Resource Relation:
- Conference: American Society of Mechanical Engineers winter meeting, Anaheim, CA, USA, 7 Dec 1986; Other Information: Technical Paper 86-WA/HT-4
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BREEDING BLANKETS
THERMAL ANALYSIS
FIELD-REVERSED MIRROR REACTORS
HYDRAULICS
THERMODYNAMICS
TOKAMAK TYPE REACTORS
CALCULATION METHODS
COOLING LOAD
CORROSION
DESIGN
EFFICIENCY
EUTECTICS
LEAD
LIQUID METALS
LITHIUM
OPTIMIZATION
PINCH DEVICES
PLANNING
POWER DENSITY
REACTOR COMPONENTS
REACTOR CORES
THERMAL STRESSES
THERMONUCLEAR REACTORS
WATER
ALKALI METALS
CHEMICAL REACTIONS
ELEMENTS
FLUID MECHANICS
FLUIDS
HYDROGEN COMPOUNDS
LIQUIDS
MAGNETIC MIRROR TYPE REACTORS
MECHANICS
METALS
OXYGEN COMPOUNDS
STRESSES
THERMONUCLEAR DEVICES
700201* - Fusion Power Plant Technology- Blanket Engineering