[en] The principal engineering features of the proposed Spherical Torus Experiment (STX) are described. Design is dominated by the small bore available for the ohmic heating (OH) solenoid and structural considerations for a situation in which B/sub p/ is approximately equal to B/sub t/. Unique features of a spherical torus plasma include large elongations without shaping fields; an exceptionally high ratio of plasma current to toroidal field, giving the potential for stability at very high beta; strong paramagnetism; and a variety of configurations, ranging from tokamak (q/sub a/) to revised-field pinch (RFP) (q/sub a/ < 1). Access to this regime requires aspect ratios less than 2. A feasibility study has been done for a beam-heated device with A = 1.67, R₀ = 0.45, and K = 2. 3 refs., 9 figs