Physics Design of the National Spherical Torus Experiment
- 1 July 1999
- journal article
- research article
- Published by Taylor & Francis in Fusion Technology
- Vol. 36 (1) , 16-37
- https://doi.org/10.13182/fst99-a88
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.Keywords
This publication has 25 references indexed in Scilit:
- High-performance discharges in the Small Tight Aspect Ratio Tokamak (START)Physics of Plasmas, 1998
- ITER L mode confinement databaseNuclear Fusion, 1997
- Ideal MHD stability limits of low aspect ratio tokamak plasmasNuclear Fusion, 1997
- Role of the stabilizing shell in high- beta , low-q disruptions in PBX-MNuclear Fusion, 1996
- High harmonic fast waves in high beta plasmasPhysics of Plasmas, 1995
- 'Natural elongation' of spherical tokamaksNuclear Fusion, 1992
- Scalings for tokamak energy confinementNuclear Fusion, 1990
- Current relaxation time scales in toroidal plasmasPhysics of Fluids B: Plasma Physics, 1989
- Characteristics of low-q disruptions in PBXNuclear Fusion, 1988
- Features of spherical torus plasmasNuclear Fusion, 1986