Engineering Overview of the National Spherical Torus Experiment (NSTX)
- Princeton Plasma Physics Laboratory, Princeton, NJ 08543 (United States)
The National Spherical Torus Experiment (NSTX) Project will provide a national facility for the study of plasma confinement, heating, and current drive in a low-aspect-ratio, spherical torus (ST) configuration. The ST configuration is an alternate confinement concept which is characterized by high beta, high elongation, high bootstrap fraction, and low toroidal magnetic field compared to conventional tokamaks. The NSTX is the next-step ST experiment following smaller experiments such as the Princeton Plasma Physics Laboratory CDX-U (Current Drive Experiment-Upgrade), the START (Small Tight Aspect Ratio Tokamak) at Culham Laboratory, UK, and the HIT (Helicity Injected Tokamak) at the University of Washington, and it is smaller in scale to the MAST (Meg-Amp Spherical Tokamak) machine now under construction at Culham.This paper provides a description of the NSTX mission and gives an overview of the main engineering features of the design of the machine and facility and discusses some of the key design solutions.
- Research Organization:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC02-CHO-3073
- OSTI ID:
- 16441
- Report Number(s):
- CFP-3862; CONF-971065*-; ON: DE98051285
- Resource Relation:
- Conference: 17th Institute of Electrical and Electronic Engineers/Nuclear and Plasma Science Society's Symposium on Fusion Engineering, San Diego, CA (USA) 10/06/97 - 10/10/97
- Country of Publication:
- United States
- Language:
- English
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