Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 49 / Number 2 / Pages 139-167
K. Hoshino, T. Yamamoto, H. Tamai, K. Ohasa, H. Kawashima, Y. Miura, T. Ogawa, T. Shoji, T. Shibata, K. Kikuchi, M. Sawahata, K. Takahashi
Fusion Science and Technology / Volume 49 / Number 2 / Pages 139-167
Format:electronic copy (download)
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.
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