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Design of a Closed Helical Divertor in LHD and the Prospect for Helical Fusion Reactors

http://hdl.handle.net/10655/00012906
http://hdl.handle.net/10655/00012906
380c77b1-c452-4236-b13b-16bdb3e00d8c
名前 / ファイル ライセンス アクション
Fusion.Sci.Techn_ Fusion.Sci.Techn_ 56_pp1001 (1.7 MB)
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Item type 学術雑誌論文 / Journal Article(1)
公開日 2022-01-20
タイトル
タイトル Design of a Closed Helical Divertor in LHD and the Prospect for Helical Fusion Reactors
言語
言語 eng
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 SHOJI, Mamoru

× SHOJI, Mamoru

SHOJI, Mamoru

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KOBAYASHI, Masahiro

× KOBAYASHI, Masahiro

KOBAYASHI, Masahiro

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MASUZAKI, Suguru

× MASUZAKI, Suguru

MASUZAKI, Suguru

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SAGARA, Akio

× SAGARA, Akio

SAGARA, Akio

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YAMADA, Hiroshi

× YAMADA, Hiroshi

YAMADA, Hiroshi

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KOMORI, Akio

× KOMORI, Akio

KOMORI, Akio

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LHD Experimental Group,

× LHD Experimental Group,

LHD Experimental Group,
LHD Experimental Groups,
the LHD Experimental Groups,
the LHD Experimental Group,

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抄録
内容記述タイプ Abstract
内容記述 A new closed helical divertor configuration for efficient particle control and reduction of the heat load on the divertor plates is proposed. The closed divertor configuration practically utilizes an ergodic layer and magnetic field line configuration on divertor legs in helical systems. For optimization of the design of the closed divertor, the distribution of the strike points is calculated in various magnetic configurations in the Large Helical Device (LHD). It suggests that the installation of the closed divertor components in the inboard side of the torus under an inward shift configuration (Rax=3.60m) is the best choice for achieving the above two purposes. This divertor configuration does not interfere with plasma heating and diagnostic systems installed in outer ports. The prospect of the closed divertor configuration to a helical fusion reactor is investigated using a three-dimensional neutral particle transport simulation code with a one-dimensional plasma fluid calculation on the divertor legs. The investigation shows efficient particle pumping from the in board side and reduction of the heat load due to the combined effect of the optimized closed divertor geometry, ergodized divertor legs, and low electron temperature in the ergodic layer. It indicates a promising closed divertor configuration for helical fusion reactors.
書誌情報 Fusion Science and Technology

巻 56, 号 2, p. 1001-1008, 発行日 2017-04-07
書誌的事項
Proceedings of the EIGHTEENTH TOPICAL MEETING ON THE TECHNOLOGY OF FUSION ENERGY (Part 2) San Francisco, California September 28–October 2, 2008
出版者
出版者 Taylor & Francis
ISSN
収録物識別子タイプ ISSN
収録物識別子 15361055
書誌レコードID
収録物識別子タイプ NCID
収録物識別子 AA11558871
DOI
関連タイプ isVersionOf
識別子タイプ DOI
関連識別子 10.13182/FST09-A9041
権利
権利情報 This is an Accepted Manuscript of an article published by Taylor & Francis in Fusion Sicence and Technology on 7 Apr. 2017, available online: http://www.tandfonline.com/doi.org/10.13182/FST09-A9041.
情報源
関連名称 To cite this article: Mamoru Shoji, Masahiro Kobayashi, Suguru Masuzaki, Akio Sagara, Hiroshi Yamada, Akio Komori & LHD Experimental Groups (2009) Design of a Closed Helical Divertor in LHD and the Prospect for Helical Fusion Reactors, Fusion Science and Technology, 56:2, 1001-1008, DOI: 10.13182/FST09-A9041
関連サイト
識別子タイプ DOI
関連識別子 https://doi.org/10.13182/FST09-A9041
関連名称 Publisher version
著者版フラグ
出版タイプ AM
出版タイプResource http://purl.org/coar/version/c_ab4af688f83e57aa
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Cite as

SHOJI, Mamoru, KOBAYASHI, Masahiro, MASUZAKI, Suguru, SAGARA, Akio, YAMADA, Hiroshi, KOMORI, Akio, the LHD Experimental Group, , 2017, Design of a Closed Helical Divertor in LHD and the Prospect for Helical Fusion Reactors: Taylor & Francis , 1001–1008 p.

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