Breeder-in-tube design for a helium-cooled Li/sub 2/O tokamak blanket
Of the solid breeder designs considered in the Blanket Comparison and Selection Study (BCSS), the lithium oxide breeder with helium coolant and ferritic steel (HT-9) structural material received the highest overall ranking for both tokamak and tandem mirror systems in terms of engineering, economics, safety, and R and D requirements. The BCSS blanket surrounding the fusion plasma consists of a number of thin breeder plates externally cooled by flowing helium and internally purged of tritium by a separate helium stream. A detailed review of this design indicated that significant improvements would be realized in the areas of tritium breeding, blanket thickness, blanket energy multiplication, power-conversion efficiency, breeder temperature window, and geometrical integrity of the coolant and purge paths by using a neutron multiplier (beryllium), a higher temperature structural material (vanadium-based alloy), and a tube geometry. The neutronics, thermal-hydraulics, tritium recovery, and structural performance characteristics of this innovative solid breeder design are discussed in this paper.
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 5503576
- Report Number(s):
- CONF-860610-; TRN: 88-008121
- 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
THERMONUCLEAR REACTORS
BREEDING PELLETS
CLADDING
HELIUM
LITHIUM OXIDES
MECHANICAL PROPERTIES
THERMONUCLEAR REACTOR COOLING SYSTEMS
TUBES
ALKALI METAL COMPOUNDS
CHALCOGENIDES
COOLING SYSTEMS
DEPOSITION
ELEMENTS
ENERGY SYSTEMS
FLUIDS
GASES
LITHIUM COMPOUNDS
NONMETALS
OXIDES
OXYGEN COMPOUNDS
RARE GASES
REACTOR COMPONENTS
SURFACE COATING
700201* - Fusion Power Plant Technology- Blanket Engineering
700204 - Fusion Power Plant Technology- Cooling Systems