Fusion Engineering Design Center/Westinghouse, Electric Corporation, Post Office Box Y, FEDC Building, Oak Ridge, Tennessee 37830, (615)576-5503 The early tokamak reactor configuration was developed as a means to identify engineering and technology problems and, if possible, suggest resolutions. The power reactor was depicted as a large device with many superconducting toroidal field (TF) coils and many distributed internal and external poloidal field (PF) coils. The mechanical configuration dictated a complicated maintenance approach. Access to the plasma chamber was limited. Particular attention has been paid, in recent reactor studies,1-3 to incorporate attractive, cost-effective engineering features to minimize the device complexity and satisfy the assembly and maintenance requirements of the various reactor components. This has been accomplished without degrading the physics operating parameters of the reactor. In the design process, a number of desirable engineering features have been identified that, when incorporated, make the tokamak a much more attractive reactor candidate Recent scoping studies examined a series of superconducting, long-pulse Driven Current Tokamak (DCT) devices. One class of options is an ignited, D-T burning device designated DCT-8. It was concluded that the DCT-8 is a most attractive engineering option to adequately bridge the gap between the Tokamak Fusion Test Reactor (TFTR) and the Engineering Test Reactor (ETR).