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Overview of the Initial NSTX Experimental Results

Conference ·
OSTI ID:1081584
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  1. Princeton Plasma Physics Laboratory (PPPL)
  2. ORNL
  3. University of California, Los Angeles
  4. Los Alamos National Laboratory (LANL)
  5. Columbia University
  6. University of Washington, Seattle
  7. Johns Hopkins University
  8. EURATOM / UKAEA, UK
  9. Massachusetts Institute of Technology (MIT)
  10. General Atomics
  11. Fusion Physics and Technology
  12. University of California, Davis
  13. University of California, San Diego
+ Show Author Affiliations
The main aim of the National Spherical Torus Experiment (NSTX) is to establish the fusion physics principles of the spherical torus (ST) concept. The NSTX device began plasma operations in February 1999 and the plasma current Ip was successfully brought up to the design value of 1 million amperes on December 14, 1999. The planned plasma shaping parameters, k = 1.6 - 2.2 and d = 0.2 - 0.4, were achieved in inner limited, single null and double null configurations. The CHI (Coaxial Helicity Injection) and HHFW (High Harmonic Fast Wave) experiments were also initiated. A CHI injected current of 27 kA produced up to 260 kA of toroidal current without using an ohmic solenoid. With an injection of 2.3 MW of HHFW power, using twelve antennas connected to six transmitters, electrons were heated from a central temperature of 400 eV to 900 eV at a central density of 3.5 x 1013 cm-3 increasing the plasma energy to 59 kJ and the toroidal beta, bT to 10 %. Finally, the NBI system commenced operation in Sept. 2000. The initial results with two ion sources (PNBI = 2.8 MW) shows good heating, producing a total plasma stored energy of 90 kJ corresponding to bT 18 % at a plasm current of 1.1 MA.
Research Organization:
Oak Ridge National Laboratory (ORNL)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1081584
Country of Publication:
United States
Language:
English

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Related Subjects

NSTX