ログイン
言語:

WEKO3

  • トップ
  • ランキング
To

Field does not validate

To

Field does not validate

To
lat lon distance


インデックスリンク

インデックスツリー

  • RootNode

メールアドレスを入力してください。

WEKO

One fine body…

WEKO

One fine body…

アイテム

  1. Published Papers
  2. Published Papers

Stability and Confinement Studies of High-Performance NBI Plasmas in the Large Helical Device Toward a Steady-State Helical Fusion Reactor

http://hdl.handle.net/10655/6361
http://hdl.handle.net/10655/6361
e2f24e5f-2475-4ead-a63b-55fb40c460fa
名前 / ファイル ライセンス アクション
pfr2008_03-S1001.pdf pfr2008_03-S1001.pdf (1.9 MB)
Item type 学術雑誌論文 / Journal Article_02(1)
公開日 2011-03-28
タイトル
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 en
言語
言語 eng
キーワード
言語 en
主題Scheme Other
主題 Large Helical Device
キーワード
言語 en
主題Scheme Other
主題 MHD stability
キーワード
言語 en
主題Scheme Other
主題 Shafranov shift
キーワード
言語 en
主題Scheme Other
主題 nternal diffusion barrier
キーワード
言語 en
主題Scheme Other
主題 ion transport
キーワード
言語 en
主題Scheme Other
主題 toroidal rotation
キーワード
言語 en
主題Scheme Other
主題 impurity hole
キーワード
言語 en
主題Scheme Other
主題 helical fusion reactor
キーワード
言語 en
主題Scheme Other
主題 neoclassical transport
キーワード
言語 en
主題Scheme Other
主題 anomalous transport
キーワード
言語 en
主題Scheme Other
主題 core electron-root confinement
資源タイプ
資源タイプ識別子 http://purl.org/coar/resource_type/c_6501
資源タイプ journal article
著者 TAKEIRI, Yasuhiko

× TAKEIRI, Yasuhiko

en TAKEIRI, Yasuhiko

Search repository
KOMORI, Akio

× KOMORI, Akio

en KOMORI, Akio

Search repository
YAMADA, Hiroshi

× YAMADA, Hiroshi

en YAMADA, Hiroshi

Search repository
KAWAHATA, Kazuo

× KAWAHATA, Kazuo

en KAWAHATA, Kazuo

Search repository
MUTOH, Takashi

× MUTOH, Takashi

en MUTOH, Takashi

Search repository
OHYABU, Nobuyoshi

× OHYABU, Nobuyoshi

en OHYABU, Nobuyoshi

Search repository
KANEKO, Osamu

× KANEKO, Osamu

en KANEKO, Osamu

Search repository
IMAGAWA, Sinsaku

× IMAGAWA, Sinsaku

en IMAGAWA, Sinsaku

Search repository
NAGAYAMA, Yoshio

× NAGAYAMA, Yoshio

en NAGAYAMA, Yoshio

Search repository
WATANABE, Kiyomasa

× WATANABE, Kiyomasa

en WATANABE, Kiyomasa


Search repository
SHIMOZUMA, Takashi

× SHIMOZUMA, Takashi

en SHIMOZUMA, Takashi

Search repository
IDA, Katsumi

× IDA, Katsumi

en IDA, Katsumi

Search repository
SAKAMOTO, Ryuichi

× SAKAMOTO, Ryuichi

en SAKAMOTO, Ryuichi

Search repository
KOBAYASHI, Masahiro

× KOBAYASHI, Masahiro

en KOBAYASHI, Masahiro

Search repository
SAGARA, Akio

× SAGARA, Akio

en SAGARA, Akio

Search repository
NAGAOKA, Kenichi

× NAGAOKA, Kenichi

en NAGAOKA, Kenichi

Search repository
YOSHINUMA, Mikiro

× YOSHINUMA, Mikiro

en YOSHINUMA, Mikiro

Search repository
SAKAKIBARA, Satoru

× SAKAKIBARA, Satoru

en SAKAKIBARA, Satoru

Search repository
SUZUKI, Yasuhiro

× SUZUKI, Yasuhiro

en SUZUKI, Yasuhiro

Search repository
YOKOYAMA, Masayuki

× YOKOYAMA, Masayuki

en YOKOYAMA, Masayuki

Search repository
SUDO, Shigeru

× SUDO, Shigeru

en SUDO, Shigeru

Search repository
MOTOJIMA, Osamu

× MOTOJIMA, Osamu

en MOTOJIMA, Osamu

Search repository
the, LHD Experimental Group

× the, LHD Experimental Group

en the, LHD Experimental Group

Search repository
抄録
内容記述タイプ Abstract
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
出版者
出版者 プラズマ・核融合学会
DOI
識別子タイプ DOI
関連識別子 10.1585/pfr.3.S1001
権利
権利情報 ? 2008 The Japan Society of Plasma Science and Nuclear Fusion Research
戻る
0
views
See details
Views

Versions

Ver.1 2023-06-20 16:40:28.234387
Show All versions

Share

Mendeley Twitter Facebook Print Addthis

Cite as

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, 2008, Stability and Confinement Studies of High-Performance NBI Plasmas in the Large Helical Device Toward a Steady-State Helical Fusion Reactor: プラズマ・核融合学会, S1001-1 -S1001-8- p.

Loading...

エクスポート

OAI-PMH
  • OAI-PMH JPCOAR 2.0
  • OAI-PMH JPCOAR 1.0
  • OAI-PMH DublinCore
  • OAI-PMH DDI
Other Formats
  • JSON
  • BIBTEX

Confirm


Powered by WEKO3


Powered by WEKO3