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Conceptual Design and Development of an Indirect-cooled Superconducting Helical Coil in the FFHR
http://hdl.handle.net/10655/6386
http://hdl.handle.net/10655/6386eb1f9199-8dda-4fa9-9034-81aae53cb621
名前 / ファイル | ライセンス | アクション |
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pfr2010_05-S1035.pdf (7.4 MB)
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Item type | 学術雑誌論文 / Journal Article_02(1) | |||||
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公開日 | 2011-04-28 | |||||
タイトル | ||||||
言語 | en | |||||
タイトル | Conceptual Design and Development of an Indirect-cooled Superconducting Helical Coil in the FFHR | |||||
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 | helical reactor | |||||
キーワード | ||||||
言語 | en | |||||
主題Scheme | Other | |||||
主題 | indirect-cooled superconducting magnet | |||||
キーワード | ||||||
言語 | en | |||||
主題Scheme | Other | |||||
主題 | Nb3Sn superconductor | |||||
キーワード | ||||||
言語 | en | |||||
主題Scheme | Other | |||||
主題 | cable-in-conduit-conductor | |||||
キーワード | ||||||
言語 | en | |||||
主題Scheme | Other | |||||
主題 | stress analysis | |||||
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 |
TAMURA, Hitoshi
× TAMURA, Hitoshi× TAKAHATA, Kazuya× MITO, Toshiyuki× IMAGAWA, Shinsaku× SAGARA, Akio |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | The force-free helical reactor (FFHR) is a conceptual design of a heliotron fusion reactor being developed at the National Institute for Fusion Science. All the coils in the FFHR are made of superconductors. Several cooling schemes have been proposed for the helical coils; of these, indirect cooling is considered a good candidate. In this study, we investigated the possibility of using an indirect-cooled superconducting magnet for the FFHR. In parallel with this design study, we developed Nb3Sn superconductors, jacketed with an aluminum alloy, for use in an indirect-cooled magnet. The results of performance tests of a sub-scale superconductor showed good feasibility for application in the FFHR helical coil. Stress distribution in the helical coil was also analyzed, and the stress and strain were confirmed to be within the permissible range. | |||||
書誌情報 |
en : Plasma and Fusion Research 巻 Vol.5, p. S1035-1 - S1035-5, 発行日 2010-01-01 |
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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.5.S1035 | |||||
権利 | ||||||
権利情報 | ? 2010 The Japan Society of Plasma Science and Nuclear Fusion Research |