Engineering Design of the National Spherical Torus Experiment
Authors: Neumeyer, C., P. Heitzenroeder, J. Spitzer, J. Chrzanowski, A. Brooks, J. Bialek, H.M. Fan, G. Barnes, M. Viola, B. Nelson, P. Goranson, R. Wilson, E. Fredd, L. Dudek, R. Parsells, M. Kalish, W. Blanchard, R. Kaita, H. Kugel, B. McCormack, S. Ramakrishnan, R. Hatcher, G. Oliaro, E. Perry, T. Egebo, A. Von Halle, M. Williams, and M. Ono.
Date of PPPL Report: May 2000
Submitted to: Fusion Engineering and DesignNSTX is a proof-of-principle experiment aimed at exploring the physics of the "spherical torus" (ST) configuration, which is predicted to exhibit more efficient magnetic confinement than conventional large aspect ratio tokamaks, amongst other advantages. The low aspect ratio (R/a, typically 1.2 ~ 2 in ST designs compared to 4 ~ 5 in conventional tokamaks) decreases the available cross sectional area through the center of the torus for toroidal and poloidal field coil conductors, vacuum vessel wall, plasma facing components, etc., thus increasing the need to deploy all components within the so-called "center stack" in the most efficient manner possible. Several unique design features have been developed for the NSTX center stack, and careful engineering of this region of the machine, utilizing materials up to their engineering allowables, has been key to meeting the desired objectives. The design and construction of the machine has been accomplished in a rapid and cost effective manner thanks to the availability of extensive facilities, a strong experience base from the TFTR era, and good cooperation between institutions.