Torus fusion reactor

Next-step D-T burning fusion reactors, such as the International Thermonuclear Experimental Reactor (ITER), will require several kilograms of tritium [1,2]. While most of the tritium will be contained in the fuel process loop, the interaction of the plasma with plasma-facing components (first-wall armour, limiters, and divertors) will lead to accumulation of tritium in the torus. Based on the amounts and distribution of D retention in TFTR and... 

The JET (Joint European Torus) nucelar fusion reactor. Photo Researchers, Inc. Reproduced by permission. 

This paper summarizes several studies of fusion reactors based on the compact torus (CT). A wide variety of reactor configurations can be projected within present understanding of the possible types of CT and their macroscopic stability and confinement properties. Three types of CT are considered here, the field-reversed-configuration having B oroidal 0, the Spheromak with 0, and CT s formed with particle rings. 

The purpose of this paper is to review some fusion reactor possibilities based on the compact torus (CT) confinement... 

Summary of U.S. Compact Torus Experiments and Fusion Reactor Aspects of the Compact Torus by C.W. HARTMAN, in present proceedings. 

Despite great strides, the problems arising from plasma-material interactions (PMIs), together with the selection of plasma facing materials, still represent major challenges for the reliable and safe operation of a D-T next-step tokamak [1]. They also remain potential obstacles for the successful development of future fusion power reactors. These issues came into sharp focus during D-T operation of the Tokamak Fusion Test Reactor (TFTR) and the Joint European Torus (JET) and, in particular, in the process of designing ITER. 

Interest in the compact torus (CT) for fusion rests on forming an axisymmetric, closed, toroidal-confinement-region for plasma within a nearly uniform external field as shown in Fig. 1. The advantages of toroidal confinement are thereby obtained while retaining reactor-related simplifications in blanket and coil design and natural plasma diversion because of the open-ended external field. To achieve these dual advantages, the toroidal confinement fields must be formed by plasma currents, rather than... 

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