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

被引：4
作者：
Utoh, Hiroyasu [1 ]
Matsunaga, Go [2 ]
Hiwatari, Ryoji [1 ]
Sakamoto, Yoshiteru [1 ]
Tobita, Kenji [1 ]
机构：
[1] Natl Inst Quantum & Radiol Sci & Technol, Aomori 0393212, Japan
[2] Natl Inst Quantum & Radiol Sci & Technol, Ibaraki 3110193, Japan
来源：
FUSION ENGINEERING AND DESIGN | 2020年 / 161卷
关键词：
DEMO design; Superconducting magnet; Toroidal field coil; Error field; Error field correction coil; OPERATIONAL LIMITS; MHD STABILITY; CHAPTER; 3;
D O I：
10.1016/j.fusengdes.2020.111900
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
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.
引用
收藏
页数：4
相关论文
共 9 条
  • [1] [Anonymous], 2009, ITERD2NPLKM 8
  • [2] From Design to Development Phase of the ITER Correction Coils
    Foussat, Arnaud
    Dolgetta, Nello
    Jong, Cornelis
    Libeyre, Paul
    Mitchell, Neil
    Wu, Weiyue
    Liu, Liping
    Du, Shuangsong
    Liu, Xufeng
    Yu, Xiaowu
    Han, Shiqiang
    Wei, Jing
    [J]. IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2011, 21 (03) : 1960 - 1963
  • [3] Gribov Y., 2012, IAEA INT C FUS EN
  • [4] Chapter 3:: MHD stability, operational limits and disruptions
    Hender, T. C.
    Wesley, J. C.
    Bialek, J.
    Bondeson, A.
    Boozer, A. H.
    Buttery, R. J.
    Garofalo, A.
    Goodman, T. P.
    Granetz, R. S.
    Gribov, Y.
    Gruber, O.
    Gryaznevich, M.
    Giruzzi, G.
    Guenter, S.
    Hayashi, N.
    Helander, P.
    Hegna, C. C.
    Howell, D. F.
    Humphreys, D. A.
    Huysmans, G. T. A.
    Hyatt, A. W.
    Isayama, A.
    Jardin, S. C.
    Kawano, Y.
    Kellman, A.
    Kessel, C.
    Koslowski, H. R.
    La Haye, R. J.
    Lazzaro, E.
    Liu, Y. Q.
    Lukash, V.
    Manickam, J.
    Medvedev, S.
    Mertens, V.
    Mirnov, S. V.
    Nakamura, Y.
    Navratil, G.
    Okabayashi, M.
    Ozeki, T.
    Paccagnella, R.
    Pautasso, G.
    Porcelli, F.
    Pustovitov, V. D.
    Riccardo, V.
    Sato, M.
    Sauter, O.
    Schaffer, M. J.
    Shimada, M.
    Sonato, P.
    Strait, E. J.
    [J]. NUCLEAR FUSION, 2007, 47 (06) : S128 - S202
  • [5] ITER non-axisymmetric error fields induced by its magnet system
    Knaster, J.
    Amoskov, V.
    Formisano, A.
    Gribov, Y.
    Lamzin, E.
    Martone, L.
    Maximenkova, N.
    Mitchell, N.
    Portone, A.
    Sytchevsky, S.
    Testoni, P.
    [J]. FUSION ENGINEERING AND DESIGN, 2011, 86 (6-8) : 1053 - 1056
  • [6] In-vessel coils for magnetic error field correction in JT-60SA
    Matsunaga, G.
    Takechi, M.
    Sakurai, S.
    Suzuki, Y.
    Ide, S.
    Urano, H.
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1113 - 1117
  • [7] Mirnov S, 1999, NUCL FUSION, V39, P2251, DOI 10.1088/0029-5515/39/12/303
  • [8] Sakamoto Y., 2018, 27 IAEA INT C FUS EN
  • [9] Japan's Efforts to Develop the Concept of JA DEMO During the Past Decade
    Tobita, Kenji
    Hiwatari, Ryoji
    Sakamoto, Yoshiteru
    Someya, Youji
    Asakura, Nobuyuki
    Utoh, Hiroyasu
    Miyoshi, Yuya
    Tokunaga, Shinsuke
    Homma, Yuki
    Kakudate, Satoshi
    Nakajima, Noriyoshi
    [J]. FUSION SCIENCE AND TECHNOLOGY, 2019, 75 (05) : 372 - 383
1