Conceptual design of a self-cooled Flibe blanket
There are a number of attractive features for Flibe, such as: (1) low-pressure operation, (2) relatively inert to air and water, (3) low activation, (4) high-temperature stability, and (5) low electrical conductivity. If these features can be incorporated into a self-cooled blanket, a simple, high-performance, and reliable blanket may be possible. Detailed analysis has uncovered some attractive features and some potential problems. A highly compact and efficient primary loop can be developed with a conversion efficiency of 46%. The blanket is designed to be inherently safe for at least a 4.7 MW/m/sup 2/ neutron wall loading. Since no reflector is needed, the mass utilization is very high. A similar blanket for MINIMARS has a mass utilization figure of 138 kW(e)/tonne, the highest among the four blanket candidates. In addition, a very simple blanket can be designed. There is, however, concern about the lithium doping idea for tritium control. The issues cannot be resolved until experimental verification is available. However, if a vanadium alloy is used for the structural material, a large fraction of tritium will permeate back through the first wall to the plasma. Permeation through the first wall will result in a tritium partial pressure of < 10/sup -4/ Torr. If this is the case, the primary blanket tritium recovery system can be combined with the plasma exhaust system. A highly efficient tritium cleanup system will still be required to reduce the tritium permeation problem. A countercurrent extraction system can be used for tritium cleanup.
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 5577775
- Report Number(s):
- CONF-860610-; TRN: 88-008075
- 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 REACTOR MATERIALS
MINIMARS REACTOR
COOLANTS
COOLING
LITHIUM TRITIDES
VANADIUM ALLOYS
ALKALI METAL COMPOUNDS
ALLOYS
HYDRIDES
HYDROGEN COMPOUNDS
LABELLED COMPOUNDS
LITHIUM COMPOUNDS
LITHIUM HYDRIDES
MAGNETIC MIRROR TYPE REACTORS
MATERIALS
REACTOR COMPONENTS
THERMONUCLEAR REACTORS
TRITIUM COMPOUNDS
700201* - Fusion Power Plant Technology- Blanket Engineering
700209 - Fusion Power Plant Technology- Component Development & Materials Testing