Estimation of magnetic error field with alleviating fabrication tolerance of large superconducting magnets on JA DEMO reactor

Joint Special D esign Team for Fusion DEMO

研究成果: ジャーナルへの寄稿学術論文査読

4 被引用数 (Scopus)

抄録

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.

本文言語英語
論文番号111900
ジャーナルFusion Engineering and Design
161
DOI
出版ステータス出版済み - 2020 12月

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