|| L D R : T h e L e v i t a t e d D i p o l e R e a c t o r
Fusion research has focused on the goal of a fusion power source that utilizes deuterium and tritium (D-T) because the reaction rate is relatively large compared with the rate for D-D or D-He3. Furthermore, the D-D cycle is difficult in a traditional fusion confinement device such as a tokamak because good energy confinement is accompanied by good particle confinement which leads to a build up of ash in the discharge.
Previous studies [1-4] indicate that a levitated dipole would be favorable for a D-He3 fuel cycle based power source. The D-D cycle is the most promising because of the availability of deuterium. Recently we have considered utilizing a levitated dipole for the D-D cycle based power source. Fusion reactors based on the deuterium-deuterium (D-D) reaction would be superior to D-T based reactors in so far as they can greatly reduce the power produced in neutrons and do not requires the breeding of tritium. In a recent article titled "Helium Catalyzed D-D Fusion in a Levitated Dipole" we have proposed a fusion power source, based on an alternative fuel cycle which we call ``helium catalyzed D-D". We have explored the application of a levitated dipole as a D-D power source and found that a dipole may have the unique capability of producing excellent energy confinement accompanied by low particle confinement. Additionally a levitated dipole device would be intrinsically steady state and extract power as surface heating, permitting a thin walled vacuum vessel and eliminating the need for a massive neutron shield. We find that a dipole based D-D power source can potentially provide a substantially better utilization of magnetic field energy with a comparable mass power density as compared to a D-T based tokamak power source.
- A. Hasegawa, Comments Plasma Phys. Controlled Fusion, 1, (1987) 147.
- A. Hasegawa, L. Chen, M. Mauel, Nucl. Fusion, 30, (1990) 2405.
- A. Hasegawa, L. Chen, M. Mauel, H. Warren, and S. Murakami, Fusion Technol. 22, (1992) 27.
- E. Teller, A. Glass, T.K. Fowler, A. Hasegawa, and J. Santarius, Fusion Technol. 22, (1992) 82.