Patent Number: 043702961
Section: summary

BACKGROUND OF THE INVENTION 1. Field of the Invention The invention is in the field of fusion reactor designs and particularly relates to ohmic heating coils for toroidal-type fusion reactors. The invention is also applicable to fusion-fission hybrid type reactors. 2. Description of the Prior Art A large number of studies have been directed to the design of toroidal-type fusion reactors as well as to the design of fusion-fission reactors. Representative studies include the following: Tokamak Experimental Power Reactor Conceptual Design, Volumes I and II, Argon National Laboratory, ANL/CTR-76-3, August 1976; Proceedings US-USSR Symposium on Fusion-Fission Reactors, July 13-16, 1976; and DCTR Fusion-Fission Energy Systems Review Meeting, Dec. 3-4, 1974, ERDA-4. In typical prior art toroidal-type fusion experiments and designs, the ohmic heating coil takes the form of a transformer positioned in the center of the toroidal configuration as illustrated, for example, in U.S. Pat. No. 3,778,343. It has long been desired to decrease the size of this OH transformer, particularly in view of the rather stringent space requirements present in existing machines. Attempts have been made, for example, to specifically design the toroidal field coils surrounding the plasma region to optimize space requirements within the toroidal region center along the main axis of the toroid. Such studies are exemplified by U.S. Pat. No. 3,859,615. The ability to utilize the interior space of a toroid would greatly relax the stringent design requirements imposed on toroidal-type fusion reactors and permit the utilization of lower current densities within the TF coils. SUMMARY OF THE INVENTION Accordingly, it is an object of the invention to increase the operating efficiency of toroidal-type fusion reactors. It is a further object of the invention to remove the ohmic heating transformer from the region of the main axis of the toroidal field coils to thereby enable radial expansion of the TF coil cross-sectional area within the region of the main axis. Yet another object of the invention is to provide a more efficient ohmic heating coupling to the plasma region of a fusion device of the toroidal-type. A further object of the invention is to provide a more efficient ohmic heating coupling for fusion-fission type reactors or power generating devices. In accordance with the principles of the invention there is provided a fusion reactor of the toroidal-type having a plasma containing toroidal fusion region for producing energy from fusion reactions. The fusion reactor comprises toroidal field generating means for producing a toroidal magnetic field in the plasma fusion region upon the passage of current therethrough. The toroidal field generating means is positioned proximate the toroidal fusion region. Ohmic heating coils are provided for ohmically heating the plasma within the plasma fusion region, and the ohmic heating coils are positioned between the fusion region and the toroidal field generating means on the side nearest the main axis of the toroidal fusion region. There is also disclosed in accordance with the principles of the invention a method of increasing efficiency of a fusion reactor of a toroidal configuration having toroidal field coils positioned substantially adjacent a toroidal fusion region and ohmic heating coils for ohmically heating plasma within the toroidal fusion region. The method comprises the step of positioning the ohmic heating coils between the toroidal fusion region and the toroidal field coils on a side nearest the main axis of the toroidal fusion region. There is also disclosed in accordance with the principles of the invention a fusion power generating means comprising a fusion power core having a toroidal fusion region, a toroidal field generating means positioned proximate the toroidal fusion region and an ohmic heating means positioned between the toroidal fusion region and the toroidal generating means. Further, the power generating means comprises means for extracting thermal energy from the fusion power core and is constructed such that the fusion power core is removable from the power generating means for replacement thereof by a replacement fusion power core.