Stability and Confinement Properties of Auxiliary Heated NSTX Discharges
- Princeton Plasma Physics Laboratory (PPPL)
- ORNL
The National Spherical Torus Experiment (NSTX) is a spherical tokamak with nominal plasma major radius R{sub 0} = 0.85m, minor radius a=0.66m, and aspect ratio A > 1.28. Typical discharge parameters are I{sub P} = 0.7-1.4 MA, B{sub t0} = 0.25-0.45 Tesla at R{sub 0}, elongation = 1.7-2.2, triangularity 0.3-0.5, line-average electron density n{sub e} = 2-5x10{sup 19} m{sup -3}, T{sub e}(0)=0.5-1.5keV, and T{sub i}(0) = 0.5-2keV. The NSTX auxiliary heating systems can routinely deliver 4.5MW of 80keV deuterium neutral beams and 3MW of 30MHz high-harmonic fast wave power. Kinetic profile diagnostics presently include a 10 channel, 30Hz multi-pulse Thomson scattering system (MPTS), a 17 channel charge exchange recombination spectroscopy (CHERS) system, a 48 chord ultra-soft X-ray (USXR) array, and a 15 chord bolometry array. Initial experiments utilizing auxiliary heating on NSTX have focused on MHD stability limits, confinement trends, studying H-mode characteristics, and performing initial power balance calculations.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Science (SC)
- DOE Contract Number:
- DE-AC05-00OR22725
- OSTI ID:
- 1022031
- Resource Relation:
- Conference: 28th EPS Conference on Contr. Fusion and Plasma Phys., Funchal, Portugal, 20010618, 20010618
- Country of Publication:
- United States
- Language:
- English
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