Heating, current drive, and advanced plasma control in JFT-2M

被引：2

作者：

Hoshino, K ^{[1
]}

Yamamoto, T ^{[1
]}

Tamai, H ^{[1
]}

Ohasa, K ^{[1
]}

Kawashima, H ^{[1
]}

Miura, Y ^{[1
]}

Ogawa, T ^{[1
]}

Shoji, T ^{[1
]}

Shibata, T ^{[1
]}

Kikuchi, K ^{[1
]}

Sawahata, M ^{[1
]}

Takahashi, K ^{[1
]}

机构：

[1] Japan Atom Energy Res Inst, Naka Fus Res Estab, Naka, Ibaraki 3110193, Japan

来源：

FUSION SCIENCE AND TECHNOLOGY | 2006年 / 49卷 / 02期

关键词：

JFT-2M tokamak; radio-frequency heating; current drive;

D O I：

10.13182/FST06-A1092

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

We briefly present the experimental results obtained using the various heating and current drive systems, such as electron cyclotron heating, fast wave, lower hybrid wave, ion cyclotron range of frequency, neutral beam injection heating, or the external coil systems or the divertor bias system developed in JFT-2M from the viewpoint of the active control of the tokamak plasma. The features and design concepts of each system are described briefly, as we had to develop such systems to carry out the physical research. The experimental findings in plasma heating, current drive, and advanced plasma control in the JFT-2M tokamak contributed to the design and experiments in the larger tokamaks and to ITER.

引用

页码：139 / 167

页数：29

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