Status and Plans for the National Spherical Torus Experimental Research Facility
Authors: M. Ono, M.G. Bell, R.E. Bell, J.M. Bialek, T. Bigelow, M. Bitter, and 148 additional authors
Date of PPPL Report: July 2005
Published in: Transactions of the Institute of Electrical Engineers of Japan: IEEJ Trans. EIS. 124:1 (Jan 2004) 1-16
An overview of the research capabilities and the future plans on the MA-class National Spherical Torus Experiment (NSTX) at Princeton is presented. NSTX research is exploring the scientific benefits of modifying the field line structure from that in more conventional aspect ratio devices, such as the tokamak. The relevant scientific issues pursued on NSTX include energy confinement, MHD stability at high beta, non-inductive sustainment, solenoid-free start-up, and power and particle handling. In support of the NSTX research goal, research tools are being developed by the NSTX team. In the ontext of the fusion energy development path being formulated in the US, an ST-based Component Test Facility (CTF) and, ultimately a high beta Demo device based on the ST, are being considered. For these, it is essential to develop high performance (high beta and high confinement), steady-state (non-inductively driven) ST operational scenarios and an efficient solenoid-free start-up concept. We will also briefly describe the Next-Step-ST (NSST) device being designed to address these issues in fusion-relevant plasma conditions.