Conceptual Design of Alborz Tokamak Poloidal Coils System

被引:2
|
作者
Mardani, M. [1 ]
Amrollahi, R. [1 ]
机构
[1] Amirkabir Univ Technol, Tehran, Iran
关键词
Poloidal coils; Elongation; Triangularity; Last closed flux surface; Confinement time;
D O I
10.1007/s10894-012-9545-1
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
The Alborz tokamak is a D-shape cross section tokamak that is under construction in Amirkabir University of Technology. One of the most important parts of tokamak design is the design of the poloidal field system. This part includes the numbers, individual position, currents and number of coil turns of the magnetic field coils. Circular cross section tokamaks have Vertical Field system but since the elongation and triangularity of plasma cross section shaping are important in improving the plasma performance and stability, the poloidal field coils are designed to have a shaped plasma configuration. In this paper the design of vertical field system and the magnetohydrodynamic equilibrium of axisymmetric plasma, as given by the Grad-Shafranov equation will be discussed. The poloidal field coils system consists of 12 circular coils located symmetrically about the equator plane, six inner PF coils and six outer PF coils. Six outer poloidal field coils (PF) are located outside of the toroidal field coils (TF), and six inner poloidal field coils are wound on the inner legs and are located outside of a vacuum vessel.
引用
收藏
页码:177 / 181
页数:5
相关论文
共 50 条
  • [21] Conceptual design of a poloidal field coil system and operation scenario for an inductively operated day-long pulsed tokamak reactor
    Univ of Tokyo, Tokyo, Japan
    Fusion Eng Des, pt C (69-77):
  • [22] Simulation, Design, Construction of Duoplasmatron and Diagnostic Neutral Beam System for Alborz Tokamak
    M. Kazemi
    R. Amrollahi
    Journal of Fusion Energy, 2018, 37 : 21 - 29
  • [23] Progress on in-vessel poloidal field coils optimization design for alternative divertor configuration studies on the EAST tokamak
    Xiao, B. J.
    Luo, Z. P.
    Li, H.
    Li, G. Q.
    Wang, L.
    Wang, Z. L.
    Xu, G. S.
    Yao, D. M.
    Zhou, Z. B.
    Calabro, G.
    Crisanti, F.
    Castaldo, A.
    Lombroni, R.
    Minucci, S.
    Ramogida, G.
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 2149 - 2152
  • [24] IMPACT OF A POLOIDAL DIVERTOR IN IGNITION TOKAMAK DESIGN
    STRICKLER, DJ
    PENG, YKM
    BROWN, TG
    DABIRI, AE
    LEE, VD
    MILLER, JB
    FUSION TECHNOLOGY, 1985, 8 (01): : 1754 - 1759
  • [25] A power circuit design for the poloidal field coils in a torus shaped plasma system
    Dursun B.
    Kurt E.
    Tekerek M.
    Journal of Energy Systems, 2019, 3 (03): : 123 - 128
  • [26] POLARIMETER DESIGN FOR MEASUREMENT OF THE POLOIDAL FIELD IN A TOKAMAK
    LEVINTON, FM
    REVIEW OF SCIENTIFIC INSTRUMENTS, 1988, 59 (08): : 1645 - 1645
  • [27] Optimization of Damavand Tokamak Poloidal Field Coils Positions and Currents with PSO Algorithm
    Mohammadi, M.
    Dini, F.
    Amrollahi, R.
    JOURNAL OF FUSION ENERGY, 2012, 31 (02) : 170 - 174
  • [28] Optimization of Damavand Tokamak Poloidal Field Coils Positions and Currents with PSO Algorithm
    M. Mohammadi
    F. Dini
    R. Amrollahi
    Journal of Fusion Energy, 2012, 31 : 170 - 174
  • [29] Optimization of positions and currents of tokamak poloidal field coils using genetic algorithms
    An, Zhu-Lin
    Liu, Xiao-Ping
    Wu, Bin
    Zha, Xue-Jun
    FUSION SCIENCE AND TECHNOLOGY, 2006, 50 (04) : 561 - 568
  • [30] POLOIDAL DIVERTOR FOR WISCONSIN TOKAMAK REACTOR DESIGN
    EMMERT, GA
    DONHOWE, JM
    MENSE, AT
    JOURNAL OF NUCLEAR MATERIALS, 1974, 53 (01) : 39 - 42