DocumentCode
2112327
Title
Diagnostic development on NSTX
Author
Johnson, D. ; Kaita, R. ; Roquemore, A.L.
Author_Institution
Plasma Phys. Lab., Princeton Univ., NJ, USA
fYear
1999
fDate
1999
Firstpage
81
Lastpage
86
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;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1999. 18th Symposium on
Conference_Location
Albuquerque, NM
Print_ISBN
0-7803-5829-5
Type
conf
DOI
10.1109/FUSION.1999.849796
Filename
849796
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