Improved thermal/MHD design of self-cooled blankets for high-power-density fusion reactors
In this work, an improved self-cooled blanket design is conceived that seeks to minimize the induced current and pressure loss, while maintaining effective cooling and power output. Standard solutions for fully developed MHD flows in rectangular ducts are utilized to describe the magnetic pressure drop in rectangular ducts in terms of the duct aspects ratio. A newly available analytical result for developing and fully developed temperatures is utilized in determining the maximum wall temperature and outlet temperature. Based on results from rectangular ducts, improved annular-type duct designs are proposed and evaluated. The results from the rectangular duct analysis indicate reduced pressure drop and increased thermal performance for large aspect ratio (ratio of duct width in the toroidal B-field direction to width normal to B-field). An infinite aspect ratio occurs for the annular duct design and it is shown that this configuration has superior characteristics as a self-cooled blanket design concept.
- OSTI ID:
- 5503709
- Report Number(s):
- CONF-860610-; TRN: 88-008088
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 52; Conference: American Nuclear Society annual meeting, Reno, NV, USA, 15 Jun 1986
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BREEDING BLANKETS
DESIGN
REACTOR COOLING SYSTEMS
MAGNETOHYDRODYNAMICS
TOKAMAK TYPE REACTORS
DUCTS
FIRST WALL
LIQUID METALS
LITHIUM
MAGNETIC FIELDS
RECTANGULAR CONFIGURATION
SHIELDING
ALKALI METALS
CONFIGURATION
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
FLUID MECHANICS
FLUIDS
HYDRODYNAMICS
LIQUIDS
MECHANICS
METALS
REACTOR COMPONENTS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
700201* - Fusion Power Plant Technology- Blanket Engineering
700204 - Fusion Power Plant Technology- Cooling Systems