Abstract
The mission of the National Spherical Torus Experiment (NSTX) is to prove the principles of spherical torus physics by producing high-βt plasmas that are noninductively sustained and whose current profiles are in steady state. The NSTX will be one of the first ultralow-aspect-ratio tori (R/a ≤1.3) to operate at high power (Pinput up to 11 MW) to produce high-βt (25 to 40%), low-collisionality, high-bootstrap-fraction (≤70%) discharges. Both radio-frequency and neutral beam heating and current drive will be employed. Built into the NSTX is sufficient configurational flexibility to study a range of operating space and the resulting dependences of the confinement, micro- and magnetohydrodynamic stability, and particle- and power-handling properties. NSTX research will be carried out by a nationally based science team.
Original language | English (US) |
---|---|
Pages (from-to) | 16-37 |
Number of pages | 22 |
Journal | Fusion Technology |
Volume | 36 |
Issue number | 1 |
DOIs | |
State | Published - Jul 1999 |
All Science Journal Classification (ASJC) codes
- General Engineering