Abstract
The National Spherical Torus Experiment (NSTX) is a low aspect-ratio fusion research facility whose research goal is to make a determination of the attractiveness of the spherical torus concept in the areas of high-β stability, confinement, current drive, and divertor physics. Remarkable progress was made in extending the operational regime of the device in FY 2002. In brief, βt of 34% and βN of 6.5 were achieved. H-mode became the main operational regime, and energy confinement exceeded conventional aspect-ratio tokamak scalings. Heating was demonstrated with the radiofrequency antenna, and signatures of current drive were observed. Current initiation with coaxial helicity injection produced discharges of 400 kA, and first measurements of divertor heat flux profiles in H-mode were made.
1 Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
2 Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543, USA
3 Columbia University, New York, NY, USA
4 University California at Los Angeles, Los Angeles, CA, USA
5 North Carolina State University, Raleigh, NC, USA
6 University Washington, Seattle, WA, USA
7 Los Alamos National Laboratory, Los Alamos, NM, USA
8 Princeton University, Princeton, NJ, USA
9 Johns Hopkins University, Baltimore, MD, USA