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ICRF Heating and High Energy Particle Production in the Large Helical Device

http://hdl.handle.net/10655/2366
http://hdl.handle.net/10655/2366
583c2efa-cabc-4437-97d1-ac4640af8796
Item type 研究報告書 / Research Paper(1)
公開日 2010-02-05
タイトル
タイトル ICRF Heating and High Energy Particle Production in the Large Helical Device
言語 en
言語
言語 eng
キーワード
言語 en
主題Scheme Other
主題 IAEA
キーワード
言語 en
主題Scheme Other
主題 fusion energy conference
キーワード
言語 en
主題Scheme Other
主題 Lyon
資源タイプ
資源タイプ識別子 http://purl.org/coar/resource_type/c_18ws
資源タイプ research report
アクセス権
アクセス権 metadata only access
アクセス権URI http://purl.org/coar/access_right/c_14cb
著者 "Mutoh, T.

× "Mutoh, T.

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Kumazawa, R.

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Seki, T.

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Saito, K.

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Watari, T.

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Torii, Y.

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Takeuchi, N.

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Yamamoto, T.

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Osakabe, M.

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Sasao, M.

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Murakami, S.

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Ozaki, T.

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Saida, T.

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Zhao, Y. P.

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Okada, H.

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Takase, Y.

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Fukuyama, A.

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Ashikawa, N.

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Emoto, M.

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Funaba, H.

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Goncharov, P.

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Goto, M.

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Ida, K.

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Idei, H.

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Ikeda, K.

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Inagaki, S.

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Isobe, M.

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Kaneko, O.

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Khlopenkov, K.

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Kobuchi, T.

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Komori, A.

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Kostrioukov, A.

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Kubo, S.

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Liang, Y.

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Masuzaki, S.

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Minami, T.

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Mito, T.

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Miyazawa, J.

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Morisaki, T.

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Morita, S.

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Muto, S.

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Nagayama, Y.

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Nakamura, Y.

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Nakanishi, H.

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Narihara, K.

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Narushima, Y.

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Nishimura, K.

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Noda, N.

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Notake, T.

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Ohdachi, S.

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Ohtake, I.

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Ohyabu, N.

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Oka, Y.

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Peterson, B. J.

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Sagara, A.

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Sakakibara, S.

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Sakamoto, R.

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Sasao, M.

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Sato, K.

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Sato, M.

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Shimozuma, T.

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Shoji, M.

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Suzuki, H.

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Takeiri, Y.

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Tamura, N.

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Tanaka, K.

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Toi, K.

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Tokuzawa, T.

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Tsumori, K.

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Watanabe, K. Y.

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Xu, Y.

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Yamada, H.

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Yamada, I.

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Yamamoto, S.

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Yokoyama, M.

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Yoshimura, Y.

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Yoshinuma, M.

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Itoh, K.

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Ohkubo, K.

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Satow, T.

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Sudo, S.

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Uda, T.

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Yamazaki, K.

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Matsuoka, K.

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Motojima, O.

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Hamada, Y.

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Fujiwara, M."

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抄録
内容記述タイプ Abstract
内容記述 "Significant progress has been made with lon-Cyclotron Range-of-Frequencies (lCRF) heating in the Large Helical Device (LHD). This is mainly due to better confinement of the helically trapped particles, and less accumulation of impurities in the region of the plasma core. During the past two years, ICRF heating power has been increased from 1.35 MW to 2.7 MW. Various wave-mode tests were carried out using minority-ion heating, second-harmonic heating, slow-wave heating, and high-density fast-wave heating at the fundamental cyclotron frequency. This fundamental heating mode extended the plasma-density range of effective ICRF heating to a value of 1 x 10^20 m^-3. This was the first successful result of this geating mode in large fusion devices. Using the minority-ion mode gave the best performance, and the stored energy reached 240 kJ using ICRF alone. This was obtained for the inward-shifted magnetic axis configuration. The improvement associated with the axis shift was common to both bulk plasma and highly accelerated particles. For the minority-ion mode, high-energy ions up to 500 keV were observed by concentrating the heating power near the plasma axis. The confinement properties of high-energy particles were studied for different magnetic axis configurations using the power-modulation technique. It confirmed that the confimement of high-energy particles with the inward-shifted configuration was better than that with the normal configuration. The impurity problem was not serious when the plasma boundary was sufficiently far from the chamber wal1. By reducing the impurity problem, it was possible to sustain the plasma for more than two minutes using ICRF alone."
書誌情報 en : Research Report NIFS-Series

発行日 2002-10-01
報告書番号
NIFS-741
ISSN
収録物識別子タイプ ISSN
収録物識別子 0915-633X
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