The Preliminary design of SUNIST-2:A Spherical Tokamak

被引：0
|
作者：
Zou, Chunlong [1 ,3 ]
Xu, Hao [1 ]
Tan, Yi [2 ]
Chen, Jian [2 ]
Du, Shuangsong [1 ]
Yang, Qingxi [1 ]
Gao, Zhe [2 ]
机构：
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
[2] Tsinghua Univ, Dept Engn Phys DEP, Beijing 100084, Peoples R China
[3] Minist Educ, Key Lab Magnet Suspens Technol & Maglev Vehicle, Chengdu, Peoples R China
来源：
FUSION ENGINEERING AND DESIGN | 2025年 / 212卷
关键词：
SUNIST-2; Spherical tokamak; Concept design; Vacuum vessel; Magnet system; CONCEPTUAL DESIGN;
D O I：
10.1016/j.fusengdes.2025.114865
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：
SUNIST-2 is the successor to the SUNIST spherical tokamak (ST), which designed through the cooperation of Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) and Tsinghua University (THU). Its major objective is to explore various startup and heating methods for ST with higher magnetic field. SUNIST-2 boasts a major radius of 0.525 m and a minor radius of 0.325 m,with a toroidal field capable of reaching up to 1 tesla. The vacuum vessel is notably large compared to the size of plasma, featuring an outer diameter of 2.27 m. This additional space is intentionally reserved for the antennas of radio frequency waves. The magnet system of SUNIST-2 comprises Toroidal Field Coil (TF), a Central Solenoid coil (CS), Poloidal Field coil (PF), Merging Compression Coils (MC), Diverter Figuration Coils (DF) and Compensation Coils (CC), all coils are crafted by cooper. Currently, both the concept design and engineering design of SUNIST-2 have been completed, and the manufacturing of the vacuum vessel and the coils have been finalized. In this paper, the key engineering features and design aspects of SUNIST, including electromagnetic parameters of SUNIST-2 are presented.
引用
收藏
页数：7
相关论文
共 50 条
  • [41] Tokamak and spherical tokamak research in Japan
    Takase, Y.
    Kikuchi, M.
    Maekawa, T.
    Matsukawa, M.
    Nagata, M.
    Nishio, S.
    Ono, Y.
    Sato, K. N.
    Tobita, K.
    FUSION SCIENCE AND TECHNOLOGY, 2007, 51 (2T) : 46 - 51
  • [42] Neutronics design for a spherical tokamak fusion-transmutation reactor
    Feng, K.M.
    Zhang, G.S.
    Guo, Z.J.
    Hejubian Yu Dengliziti Wuli/Nuclear Fusion and Plasma Physics, 2001, 21 (01):
  • [43] Toroidal field coil design for the spherical tokamak power plant
    Voss, GM
    Bond, A
    Edwards, JEG
    Hender, TC
    FUSION ENGINEERING AND DESIGN, 2000, 48 (3-4) : 407 - 418
  • [44] Conceptual design of a component test facility based on the spherical tokamak
    Voss, G. M.
    Davis, S.
    Dnestrovskij, A.
    Kirk, A.
    Knight, P. J.
    Loughlin, M.
    O'Brien, M. H.
    Sychugov, D.
    Tabasso, A.
    Wilson, H. R.
    FUSION ENGINEERING AND DESIGN, 2008, 83 (10-12) : 1648 - 1653
  • [45] The role of the spherical tokamak in clarifying tokamak physics
    Morris, AW
    Akers, RJ
    Connor, JW
    Counsell, GF
    Fonck, RJ
    Gryaznevich, MP
    Gusev, V
    Hender, TC
    Kaye, SM
    Maddison, GP
    Majeski, R
    Martin, TJ
    McClements, KG
    Medvedev, S
    Peng, YKM
    Roach, CM
    Robinson, DC
    Sharapov, S
    Sykes, A
    Valovic, M
    Walsh, MJ
    Wilson, HR
    PLASMA PHYSICS AND CONTROLLED FUSION, 1999, 41 : B191 - B207
  • [46] Role of the spherical tokamak in clarifying tokamak physics
    Morris, A.W.
    Akers, R.J.
    Connor, J.W.
    Counsell, G.F.
    Fonck, R.J.
    Gryaznevich, M.P.
    Gusev, V.
    Hender, T.C.
    Kaye, S.M.
    Maddison, G.P.
    Majeski, R.
    Martin, T.J.
    McClements, K.G.
    Medvedev, S.
    Peng, Y.-K.M.
    Roach, C.M.
    Robinson, D.C.
    Sharapov, S.
    Sykes, A.
    Valovic, M.
    Walsh, M.J.
    Wilson, H.R.
    Plasma Physics and Controlled Fusion, 1999, 41 (12 SUPPL.):
  • [47] The Influence of Confinement Scaling on Spherical Tokamak Power Plant Design and Performance
    Ashe, Christopher
    Muldrew, Stuart I.
    IEEE TRANSACTIONS ON PLASMA SCIENCE, 2024, 52 (09) : 3985 - 3991
  • [48] Design of the plasma facing components for the National Spherical Tokamak Experiment (NSTX)
    Goranson, P
    Barnes, G
    Chrzanowski, J
    Heitzenroeder, P
    Nelson, B
    Neumeyer, C
    Ping, J
    18TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, 1999, : 67 - 70
  • [49] Circuit design for doubling the toroidal magnetic field on the QUEST spherical tokamak
    Onchi, Takumi
    Idei, Hiroshi
    Yanagi, Nagato
    Zhang, Yifan
    Nakamura, Kazuo
    Kuroda, Kengoh
    Hasegawa, Makoto
    Ikezoe, Ryuya
    Hanada, Kazuaki
    Ido, Takeshi
    Kobayashi, Masahiro
    Ogawa, Yuichi
    Yoshitani, Minoru
    Kawamura, Takemi
    FUSION ENGINEERING AND DESIGN, 2023, 192
  • [50] Conceptual design of a heavy ion beam probe for the QUEST spherical tokamak
    Ido, T.
    Hasegawa, M.
    Ikezoe, R.
    Onchi, T.
    Hanada, K.
    Idei, H.
    Kuroda, K.
    Nagashima, Y.
    REVIEW OF SCIENTIFIC INSTRUMENTS, 2022, 93 (11):
12345