TY - JOUR
T1 - Estimation of magnetic error field with alleviating fabrication tolerance of large superconducting magnets on JA DEMO reactor
AU - Joint Special D esign Team for Fusion DEMO
AU - Utoh, Hiroyasu
AU - Matsunaga, Go
AU - Hiwatari, Ryoji
AU - Sakamoto, Yoshiteru
AU - Tobita, Kenji
N1 - Publisher Copyright:
© 2020 Elsevier B.V.
PY - 2020/12
Y1 - 2020/12
N2 - 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.
AB - 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.
KW - DEMO design
KW - Error field
KW - Error field correction coil
KW - Superconducting magnet
KW - Toroidal field coil
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U2 - 10.1016/j.fusengdes.2020.111900
DO - 10.1016/j.fusengdes.2020.111900
M3 - Article
AN - SCOPUS:85088743939
SN - 0920-3796
VL - 161
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
M1 - 111900
ER -