Control of Neoclassical Tearing Mode by Electron Cyclotron Current Drive and Non-Resonant Helical Field Application in ITER
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概要
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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.
著者
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Yamazaki Kozo
Department Of Nuclear Engineering Faculty Of Engineering University Of Tokyo
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Shoji Tatsuo
Department Of Energy Engineering And Science Nagoya University
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Arimoto Hideki
Department Of Energy Engineering And Science Nagoya University
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Taniguchi Satoshi
Department Of Anesthesiology Kyoto Prefectural University Of Medicine
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OISHI Tetsutarou
Department of Energy Engineering and Science, Graduate School of Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8093, Japan
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OISHI Tetsutarou
Department of Materials, Physics and Energy Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan
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OISHI Tetsutarou
Department of Energy Engineering and Science, Graduate School of Engineering, Nagoya University
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YAMAZAKI Kozo
Department of Energy Engineering and Science, Graduate School of Engineering, Nagoya University
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SHOJI Tatsuo
Department of Materials, Physics and Energy Engineering, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan
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Shoji Tatsuo
Department of Electronics, Tohoku Institute of Technology
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