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Observations of Anisotropic Ion Temperature in the NSTX Edge during RF Heating.

DE2004828257

Publication Date	2004
Personal Author	Biewer, T. M.; Bell, R. E.; Ryan, P. M.; Wilson, J. R.
Page Count	12
Abstract	A new spectroscopic diagnostic with both toroidal and poloidal views has been implemented in the edge of the National Spherical Torus Experiment (NSTX). This edge rotation diagnostic (ERD) was designed to measure the velocity and temperature of ions. The intersection of the diagnostic sightlines with the intrinsic emission shell provides the localization of the measurement. There are 7 toroidally directed views and 6 poloidally directed views of the outboard plasma edge. The poloidal view is (approx)20 cm (toroidally) from the RF antenna, and the toroidal view is (approx)2 m away. The sightlines are nearly tangent to the flux surfaces. The C(sup 2+) triplet near 4651 (angstrom) and the He(sup +) line at 4685 (angstrom) are measured. In the results presented here, helium is the bulk, ''working'' ion of the discharge. The NSTX is a large spherical tokamak with a major radius of 0.85 m and a minor radius of 0.65 m. The outer walls and center-stack are lined with protective carbon tiles. Pulse lengths for these NSTX discharges are (approx) 600 ms, with an on-axis toroidal magnetic field of (approx) 0.3 T. The plasma current is 500 kA. The on-axis electron temperature and density are (le) 2 keV and (approx) 2 x 10(sup 19) m(sup -3), respectively with (le) 4.3 MW of High Harmonic Fast Wave (HHFW) Radio Frequency (RF) auxiliary heating.
Keywords	Heating NSTX device Carbon Electron temperature Harmonics Helium I Ion temperature Plasma Rotation Magnetic fields
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Princeton Univ., NJ. Plasma Physics Lab.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200512

Observations of Anisotropic Ion Temperature in the NSTX Edge during RF Heating.

Observations of Anisotropic Ion Temperature in the NSTX Edge during RF Heating.
DE2004828257

Publication Date	2004
Personal Author	Biewer, T. M.; Bell, R. E.; Ryan, P. M.; Wilson, J. R.
Page Count	12
Abstract	A new spectroscopic diagnostic with both toroidal and poloidal views has been implemented in the edge of the National Spherical Torus Experiment (NSTX). This edge rotation diagnostic (ERD) was designed to measure the velocity and temperature of ions. The intersection of the diagnostic sightlines with the intrinsic emission shell provides the localization of the measurement. There are 7 toroidally directed views and 6 poloidally directed views of the outboard plasma edge. The poloidal view is (approx)20 cm (toroidally) from the RF antenna, and the toroidal view is (approx)2 m away. The sightlines are nearly tangent to the flux surfaces. The C(sup 2+) triplet near 4651 (angstrom) and the He(sup +) line at 4685 (angstrom) are measured. In the results presented here, helium is the bulk, ''working'' ion of the discharge. The NSTX is a large spherical tokamak with a major radius of 0.85 m and a minor radius of 0.65 m. The outer walls and center-stack are lined with protective carbon tiles. Pulse lengths for these NSTX discharges are (approx) 600 ms, with an on-axis toroidal magnetic field of (approx) 0.3 T. The plasma current is 500 kA. The on-axis electron temperature and density are (le) 2 keV and (approx) 2 x 10(sup 19) m(sup -3), respectively with (le) 4.3 MW of High Harmonic Fast Wave (HHFW) Radio Frequency (RF) auxiliary heating.
Keywords	Heating NSTX device Carbon Electron temperature Harmonics Helium I Ion temperature Plasma Rotation Magnetic fields
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Princeton Univ., NJ. Plasma Physics Lab.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200512