Initial Results from the National Spherical Torus Experiment (NSTX)
- and others
With a small, high-power density, and compact fusion core, Spherical Tori (ST) can provide an attractive path to a reactor or a volumetric neutron source. The National Spherical Torus Experiment (NSTX) is a proof-of-principle experiment that will explore the physics of low aspect ratio in scientifically interesting and aggressive regimes. To accomplish this mission, NSTX is designed to produce plasmas with R/a = 0.85 m/0.68 m {approximately} 1.25, I{sub p} = 1 MA, B{sub T} {le} 0.6 T, {kappa} {le} 2.2, {delta} {le} 0.5, heating powers of up to 11 MW (6 MW High Harmonic Fast Waves, 5 MW, 80 keV, D{sup 0} Neutral Beam Injection), and operation over a wide range of shapes and configurations. The OH solenoid and PF coils on NSTX are capable of producing approximately 1 V-sec of inductive flux, which, alone, is sufficient for plasma breakdown and for increasing the plasma current to the MA level. Breakdown, however, will be assisted by EC preionization. Co-axial Helicity Injection (CHI){sup 4} provides the opportunity for V-sec savings during breakdown as well as for completely non-inductive startup to about 500 kA.
- Research Organization:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Organization:
- USDOE Office of Energy Research (ER) (US)
- DOE Contract Number:
- AC02-76CH03073
- OSTI ID:
- 7634
- Report Number(s):
- Cfpaper-4029; TRN: US0101801
- Resource Relation:
- Conference: European Physical Society, Maashricht (NL), 06/14/1999--06/18/1999; Other Information: PBD: 1 Jun 1999
- Country of Publication:
- United States
- Language:
- English
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