Understanding plasma/complex surfaces interactions in NSTX with liquid lithium on thin porous molybdenum substrate for the divertor, additional PFC surfaces such as carbon tiles, and the presence of gases and impurities require integrated implementation and the interplay of detail various physical processes. These include simultaneous and multiple ion species penetration and mixing, scattering,...

A new diagnostic technique was developed to produce high-resolution impurity transport measurements of the steep-gradient edge of fusion plasmas. Perturbative impurity transport measurements were performed for the first time in the NSTX plasma edge (r/a ∼ 0.6 to the SOL) with short neon gas puffs, and the resulting line and continuum emission was measured with the new edge multi-energy soft-x-r...

RF heating and current drive is an essential component in most magnetic fusion devices, including ITER. Recent results obtained with high harmonic fast wave (HHFW) heating and current drive (CD) on NSTX strongly support the hypothesis that the onset of perpendicular fast wave propagation right at or very near the launcher is a primary cause for reduced core heating efficiency at long wavelength...

This paper presents the first control algorithm for the innerand outer-strike point position for a Spherical Torus (ST) fusion experiment and the performance analysis of the controller. A liquid lithium divertor (LLD) will be installed on NSTX which is believed to provide better pumping than lithium coatings on carbon PFCs. The shape of the plasma dictates the pumping rate of the lithium by cha...