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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.

  1. A. Hasegawa, Comments Plasma Phys. Controlled Fusion, 1, (1987) 147.
  2. A. Hasegawa, L. Chen, M. Mauel, Nucl. Fusion, 30, (1990) 2405.
  3. A. Hasegawa, L. Chen, M. Mauel, H. Warren, and S. Murakami, Fusion Technol. 22, (1992) 27.
  4. E. Teller, A. Glass, T.K. Fowler, A. Hasegawa, and J. Santarius, Fusion Technol. 22, (1992) 82.

 

Webmaster: D. Garnier Last updated: Mon, Nov 24, 2003