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

Volume

2

fYear

1997

fDate

6-10 Oct 1997

Firstpage

729

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;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1997. 17th IEEE/NPSS Symposium

Conference_Location

San Diego, CA

Print_ISBN

0-7803-4226-7

Type

conf

DOI

10.1109/FUSION.1997.687729

Filename

687729