NSTX Progress and Plan of Interest to Component Test Facility (CTF)

Continued rapid progress on NSTX and more broadly in Tokamak and ST plasma science has indicated relatively robust physics conditions in a broad number of topical areas for a compact CTF [1], which is included in the DOE Office of Science Strategic Plan [2]. This progress has enabled an updated projection of the practical CTF plasma conditions. The results indicate appropriate designs with R$_{0}$ = 1.1-1.2 m, A = 1.5, elongation $\sim $ 3, B$_{T} \quad \sim $ 1.5-2.5 T, and a range of I$_{p}$ = 6-12 MA to deliver a fusion neutron flux of 0.5-4.0 MW/m$^{2}$, requiring a range of 30-70 MW of combined neutral beam and RF heating and current drive power. Database is evaluated to be adequate in Macroscopic Plasma Physics; Multi-scale Plasma Physics; Waves and Energetic Particles; and Physics Integration; but not yet adequate in Plasma Boundary Interface (high divertor heat flux) and Solenoid-Free Operations (current initiation and ramp-up). Near-term ST research to strengthen and fill in the needed database will be described, including a discussion on how the CTF testing program could begin with plasma facing component testing in D-D at low currents followed by fusion component testing in D-T at higher currents. [1] Plasma Phys. Contol. Fusion \textbf{47} (2005) B263. [2] http://www.sc.doe.gov/bes/archives/plans/SCSP{\_}12FEB04.pdf.