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Estimation of magnetic error field with alleviating fabrication tolerance of large superconducting magnets on JA DEMO reactor
https://repo.qst.go.jp/records/82095
https://repo.qst.go.jp/records/82095f2aa656b-5d70-463c-9a5e-07af7b32b4ad
Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2021-03-09 | |||||
タイトル | ||||||
タイトル | Estimation of magnetic error field with alleviating fabrication tolerance of large superconducting magnets on JA DEMO reactor | |||||
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 | |||||
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 |
Utoh, Hiroyasu
× Utoh, Hiroyasu× Go, Matsunaga× Hiwatari, Ryoji× Yoshiteru, Sakamoto× Kenji, Tobita× Special Design Team for Fusion DEMO, Joint× Go, Matsunaga× Ryoji, Hiwatari× Yoshiteru, Sakamoto× Kenji, Tobita |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | Generally, DEMO requires larger toroidal field (TF) coils than ITER, resulting in one of the major difficulties, the tolerance in TF coil fabrication. This paper presents the possible solutions based on the design study on Japan’s DEMO (JA DEMO). It was confirmed that, in the case of adopting a mitigated tolerance by a factor of 2.5–5 compared with that of ITER, the resulting error field of TF coils is correctable to an acceptable level in terms of locked mode avoidance. In addition, the design of the error field correction coil (EFCC) on JA DEMO was investigated. | |||||
書誌情報 |
Fusion Engineering and Design 巻 161, p. 111900, 発行日 2020-12 |
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ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 0920-3796 | |||||
DOI | ||||||
識別子タイプ | DOI | |||||
関連識別子 | 10.1016/j.fusengdes.2020.111900 | |||||
関連サイト | ||||||
識別子タイプ | URI | |||||
関連識別子 | https://www.sciencedirect.com/science/article/pii/S0920379620304488 |