Plasma and Fusion Research

Volume 5, S2035 (2010)

Regular Articles

Control of Neoclassical Tearing Mode by Electron Cyclotron Current Drive and Non-Resonant Helical Field Application in ITER

Satoshi TANIGUCHI, Kozo YAMAZAKI, Tetsutarou OISHI, Hideki ARIMOTO and Tatsuo SHOJI

: Department of Materials, Physics and Energy Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan

(Received 9 December 2009 / Accepted 24 May 2010 / Published 10 December 2010)

Abstract

On tokamak plasmas like ITER, it is necessary to stabilize neoclassical tearing mode (NTM) because the NTM reduces plasma temperature and fusion power output. For the analysis of stabilizing NTM in fusion plasmas, the electron cyclotron current drive (ECCD) and the non-resonant external helical field (NRHF) application are simulated using the 1.5-dimensional equilibrium/transport simulation code (TOTAL code). The 3/2 NTM is stabilized by only external helical field, but the 2/1 mode is not stabilized by only external helical field in the present model. The stabilization time becomes shorter by the combination of ECCD and NRHF than that by ECCD alone.

Keywords

tokamak, ITER, neoclassical tearing mode, electron cyclotron current drive, non-resonant helical field

DOI: 10.1585/pfr.5.S2035

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This paper may be cited as follows:

Satoshi TANIGUCHI, Kozo YAMAZAKI, Tetsutarou OISHI, Hideki ARIMOTO and Tatsuo SHOJI, Plasma Fusion Res. 5, S2035 (2010).