Exploration of spherical torus physics in the NSTX device

The National Spherical Torus Experiment (NSTX) is being built at Princeton Plasma Physics Laboratory to test the fusion physics principles for the sph erical torus concept at the MA level. The NSTX nominal plasma parameters ar e R-o = 85 cm; a = 67 cm, R/a greater than or equal to 1.26, B-t = 3 kG, I- p = 1 MA, q(95) = 14, elongation k less than or equal to 2.2, triangularity delta less than or equal to 0.5 and a plasma pulse length of up to 5 s. Th e plasma heating/current drive tools are high harmonic fast wave (6 MW, 5 s ), neutral beam injection (5 MW, 80 keV, 5 s) and coaxial helicity injectio n. Theoretical calculations predict that NSTX should provide exciting possi bilities for exploring a number of important new physics regimes, including very high plasma beta, naturally high plasma elongation, high bootstrap cu rrent fraction, absolute magnetic well and high pressure driven sheared flo w. In addition, the NSTX programme plans to explore fully non-inductive pla sma startup as well as a dispersive scrape-off layer for heat and particle flux handling.