Title :
Physics overview of CIT
Author_Institution :
Plasma Phys. Lab., Princeton Univ., NJ, USA
Abstract :
The physics parameters and operational modes of the CIT (Compact Ignition Tokamak), are set by a combination of detailed analysis and extrapolation from the existing tokamak database, are described. Some of the innovations being incorporated into the CIT design include sweeping of the separatrix across the divertor plates to spread the heat load, two-timescale radial position control utilizing both internal and external poloidal-field coils, optimized plasma shape control using a digital controller, and fusion burn control by modulating the heat source. Models of disrupting plasmas, developed to compute structural loads, are described. The models include the effects of induced currents in the plasma halo region in which field lines intersect the vessel walls
Keywords :
Tokamak devices; fusion reactor operation; fusion reactor theory and design; position control; CIT; Compact Ignition Tokamak; digital controller; disrupting plasmas; fusion burn control; induced currents; operational modes; physics parameters; plasma halo region; plasma shape control; poloidal-field coils; two-timescale radial position control; Databases; Extrapolation; Ignition; Physics; Plasma sources; Position control; Shape control; Technological innovation; Temperature control; Tokamaks;
Conference_Titel :
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location :
Knoxville, TN
DOI :
10.1109/FUSION.1989.102443