Physics results from the National Spherical Torus Experiment

Bell, M.G.

Princeton University. Plasma Physics Laboratory.

关键词: Research Programs;    Nstx Device;    70 Plasma Physics And Fusion Technology;    Plasma Confinement;    Plasma Heating;   

DOI  :  10.2172/756898
RP-ID  :  PPPL-3459
RP-ID  :  AC02-76CH03073
RP-ID  :  756898

美国|英语

来源: UNT Digital Library

【 摘 要 】

The National Spherical Torus Experiment (NSTX) at the Princeton Plasma Physics Laboratory is designed for studying toroidal plasma confinement at very low aspect-ratio, A=R/a = 0.85m/0.68m {approximately} 1.25, with cross-section elongation up to 2.2 and triangularity up to 0.5, for plasma currents up to 1 MA and vacuum toroidal magnetic fields up to 0.6 T on axis. Conducting plates are installed close to the plasma on the outboard side to stabilize kink modes. This should permit operation with toroidal-{beta} approaching 40%. The plasmas will be heated by up to 6 MW High-Harmonic Fast Waves (HHFW) at a frequency 30 MHz and by 5 MW of 80 keV deuterium Neutral Beam Injection. Inductive plasma startup can be supplemented by the process of Coaxial Helicity Injection (CHI).