Title :
Advanced regimes in ITER with non-inductive current drive
Author :
Karulin, N. ; Boucher, D. ; Putvinski, S.
Author_Institution :
Kurchatov (I.V.) Inst. of Atomic Energy, Moscow, Russia
Abstract :
1.5 D transport code ASTRA has been used for analysis of ITER Steady-State (SS) operation scenarios driven by a combination of ECR and NB heating and current drive systems. The Current Drive (CD) systems were used in the simulations for sustaining non-inductive current profiles with negative shear and transport barrier near r/a=0.6-0.75. It is shown that 100 MW of auxiliary power is sufficient to provide high Q steady-state operation in ITER. It was found that the transport barrier does not lead to an excessive He accumulation and the advanced scenarios are not limited by the Greenwald density limit. However, these scenarios require high beta operation
Keywords :
Tokamak devices; fusion reactor theory; plasma beam injection heating; plasma radiofrequency heating; plasma toroidal confinement; plasma transport processes; ASTRA; Greenwald density limit; ITER steady-state operation scenarios; high Q steady-state operation; high beta operation; negative shear; noninductive current drive; noninductive current profiles; transport barrier; Helium; Niobium; Plasma confinement; Plasma properties; Plasma temperature; Plasma transport processes; Steady-state; Thermal conductivity; Tokamaks; Toroidal magnetic fields;
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
DOI :
10.1109/FUSION.1997.687729
