Item type |
学術雑誌論文 / Journal Article_02(1) |
公開日 |
2011-03-28 |
タイトル |
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言語 |
en |
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タイトル |
Stability and Confinement Studies of High-Performance NBI Plasmas in the Large Helical Device Toward a Steady-State Helical Fusion Reactor |
言語 |
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言語 |
eng |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
Large Helical Device |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
MHD stability |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
Shafranov shift |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
nternal diffusion barrier |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
ion transport |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
toroidal rotation |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
impurity hole |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
helical fusion reactor |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
neoclassical transport |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
anomalous transport |
キーワード |
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言語 |
en |
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主題Scheme |
Other |
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主題 |
core electron-root confinement |
資源タイプ |
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資源タイプ識別子 |
http://purl.org/coar/resource_type/c_6501 |
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資源タイプ |
journal article |
著者 |
TAKEIRI, Yasuhiko
KOMORI, Akio
YAMADA, Hiroshi
KAWAHATA, Kazuo
MUTOH, Takashi
OHYABU, Nobuyoshi
KANEKO, Osamu
IMAGAWA, Sinsaku
NAGAYAMA, Yoshio
WATANABE, Kiyomasa
SHIMOZUMA, Takashi
IDA, Katsumi
SAKAMOTO, Ryuichi
KOBAYASHI, Masahiro
SAGARA, Akio
NAGAOKA, Kenichi
YOSHINUMA, Mikiro
SAKAKIBARA, Satoru
SUZUKI, Yasuhiro
YOKOYAMA, Masayuki
SUDO, Shigeru
MOTOJIMA, Osamu
the, LHD Experimental Group
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抄録 |
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内容記述タイプ |
Abstract |
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内容記述 |
Recent progress in plasma performance and the understanding of the related physics in the Large Helical Device is overviewed. The volume-averaged beta value is increased with an increase in the neutral beam injection (NBI) heating power, and it reached 5.0% of the reactor-relevant value. In high-β plasmas, the plasma aspect ratio should be controlled so that the Shafranov shift would be reduced, mainly to suppress transport degradation and the deterioration of the NBI heating efficiency. The operational regime of a high-density plasma with an internal diffusion barrier (IDB) has been extended, and the IDB, which was originally found using the local island divertor, has been realized in the helical divertor configuration. The central density was recorded as high as 1 × 1021 m-3, and the central pressure reached 130 kPa. Based on these high-density plasmas with the IDB, a new ignition scenario has been proposed. This should be a scenario specific to the helical fusion reactor, in which the helical ripple transport would be mitigated. A low-energy positive-NBI system was newly installed for an increase in the direct ion heating power. As a result, the ion temperature (Ti) exceeded 5.2 keV at a density of 1.2 × 1019 m-3 in a hydrogen plasma. Transport analysis shows improvement of ion transport, and the Ti-increase tends to be accompanied by a large toroidal rotation velocity of the order of 50 km/s in the core region. The plasma properties in the extended operational regime are discussed from the perspective of a steady-state helical fusion reactor. |
書誌情報 |
en : Plasma and Fusion Research
巻 Vol.3,
p. S1001-1 -S1001-8,
発行日 2008-01-01
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出版者 |
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出版者 |
プラズマ・核融合学会 |
DOI |
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識別子タイプ |
DOI |
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関連識別子 |
10.1585/pfr.3.S1001 |
権利 |
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権利情報 |
? 2008 The Japan Society of Plasma Science and Nuclear Fusion Research |