Title :
Diagnostic development on NSTX
Author :
Johnson, D. ; Kaita, R. ; Roquemore, A.L.
Author_Institution :
Plasma Phys. Lab., Princeton Univ., NJ, USA
Abstract :
Diagnostics are described which are currently installed or under active development for the newly commissioned NSTX device. The low aspect ratio (R/a⩽1.3) and low toroidal field (0.1-0.3 T) used in this device dictate adaptations in many standard diagnostic techniques. Technical summaries of each diagnostic are given, and adaptations, where significant, are highlighted
Keywords :
fusion reactor instrumentation; plasma diagnostics; plasma toroidal confinement; 0.1 to 0.3 T; NSTX; National Spherical Torus Experiment; diagnostic development; fusion reactor; Coils; Geometry; Heating; Magnetic sensors; Plasma devices; Plasma diagnostics; Plasma sources; Solenoids; Tiles; Tokamaks;
Conference_Titel :
Fusion Engineering, 1999. 18th Symposium on
Conference_Location :
Albuquerque, NM
Print_ISBN :
0-7803-5829-5
DOI :
10.1109/FUSION.1999.849796
