Evaluation of AC losses in toroidal field magnets in the China Fusion Engineering Test Reactor

被引:0
|
作者
Xu, Weiwei [1 ]
Liu, Xufeng [1 ]
Zheng, Jinxing [1 ]
Du, Shuangsong [1 ]
Ni, Xiaojun [1 ]
Zou, Chunlong [1 ]
Li, Ming [1 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, Shushanhu Rd 350, Hefei 230031, Peoples R China
关键词
AC loss; Hysteresis loss; Coupling losses; Plasma disruption; STATE;
D O I
10.1016/j.fusengdes.2022.113200
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
Toroidal field (TF) superconducting magnets are the key components of the China Fusion Engineering Test Reactor (CFETR). While the TF magnets operate in a steady-state, they are located in a time-varying poloidal field environment, which may lead to AC losses. In this paper, the AC losses of a CFETR TF magnet during excitation and plasma disruption were analyzed. According to the experimental data, the relationship between the critical current density and the magnetic field (Jc-B) was obtained, allowing the hysteresis loss of a TF magnet to be calculated. The results show that the hysteresis loss during excitation is high, at about 1.26 MJ. The coupling loss of a TF magnet can be evaluated when the time constant of a conductor is obtained theoretically. The AC losses of TF magnet joints were analyzed by the same method, which showed that they are much less than those of a TF magnet.
引用
收藏
页数:8
相关论文
共 50 条
  • [21] Design and thermal-hydraulic evaluation of helium-cooled ceramic breeder blanket for China fusion engineering test reactor
    Lei, Mingzhun
    Xu, Shuling
    Guo, Chao
    Liu, Sumei
    Song, Yuntao
    Lu, Kun
    Pei, Kun
    Xu, Kun
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2018, 42 (04) : 1657 - 1663
  • [22] Concept design of 100 kA hybrid DC breaker on China fusion engineering test reactor
    Hu, Xingguang
    Li, Hua
    Song, Zhiquan
    Ren, Zhigang
    Wang, Shusheng
    Tang, Cunwen
    Fu, Peng
    FUSION ENGINEERING AND DESIGN, 2020, 158
  • [23] Activation analysis of coolant in a water-cooled loop of China fusion engineering test reactor
    Guo, Qingyang
    Zhang, Jingyu
    Fang, Sheng
    Chen, Yixue
    FUSION ENGINEERING AND DESIGN, 2018, 136 : 694 - 698
  • [24] Neutronics analysis of the ion cyclotron resonance heating antenna of the China Fusion Engineering Test Reactor
    Wang, Gaoxiang
    Qin, Chengming
    Zheng, Shanliang
    Wang, Yongsheng
    Xu, Kun
    Ma, Huiqiang
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 56 (08) : 3236 - 3241
  • [25] THE IEA LARGE COIL TASK - DEVELOPMENT OF SUPERCONDUCTING TOROIDAL FIELD MAGNETS FOR FUSION POWER
    BEARD, DS
    KLOSE, W
    SHIMAMOTO, S
    VECSEY, G
    FUSION ENGINEERING AND DESIGN, 1988, 7 (1-2) : 1 - &
  • [26] Stress analysis of toroidal field magnets of the HL-1 Tokamak of China
    Xidian Univ, Xi'an, China
    IEEE Trans Magn, 3 pt 2 (2228-2232):
  • [27] Anomalous fast ion losses at high β on the tokamak fusion test reactor
    Fredrickson, E. D.
    Bell, M. G.
    Budny, R. V.
    Darrow, D. S.
    White, R.
    PHYSICS OF PLASMAS, 2015, 22 (03)
  • [28] STUDY OF STOCHASTIC TOROIDAL FIELD RIPPLE LOSSES OF CHARGED FUSION PRODUCTS AT THE MIDPLANE OF TFTR
    BOIVIN, RL
    ZWEBEN, SJ
    WHITE, RB
    NUCLEAR FUSION, 1993, 33 (03) : 449 - 465
  • [29] Design of the cryogenic loop for the superconducting toroidal-field magnets of the Divertor Tokamak Test
    Lisanti, Fabrizio
    Angelucci, Morena
    Bonifetto, Roberto
    Michel, Frederic
    Duri, Davide
    Frattolillo, Antonio
    Froio, Antonio
    Iaboni, Andrea
    Migliori, Silvio
    Roussel, Pascal
    Zanino, Roberto
    CRYOGENICS, 2023, 136
  • [30] DTT toroidal field conductor samples test in Sultan: DC and AC characterization
    Zignani, C. Fiamozzi
    De Marzi, G.
    Scarantino, G.
    Di Zenobio, A.
    Muzzi, L.
    Turtu, S.
    Bonifetto, R.
    Zappatore, A.
    Polli, G. M.
    Ramogida, G.
    Bajas, H.
    Ortino, M.
    Sedlak, K.
    SUPERCONDUCTOR SCIENCE & TECHNOLOGY, 2024, 37 (07):