The design and optimisation of tokamak poloidal field systems in the BLUEPRINT framework

被引:6
|
作者
Coleman, M. [1 ,2 ]
McIntosh, S. [1 ,3 ]
机构
[1] United Kingdom Atom Energy Author, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[2] Univ Cambridge, Dept Engn, Trumpington St, Cambridge CB2 1PZ, England
[3] ITER Org, Route Vinon Sur Verdon,CS 90 046, F-13067 St Paul Les Durance, France
基金
英国工程与自然科学研究理事会;
关键词
Systems codes; DEMO; Plasma equilibria; Magnets; Design optimisation; PLASMA EQUILIBRIUM; COILS; POSITIONS; DEVICE; MODEL;
D O I
10.1016/j.fusengdes.2020.111544
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
As part of our aim to develop a reactor design framework, we present here our approach to the optimisation of plasma equilibria and tokamak poloidal field systems. A 2-D, free boundary, ideal magneto-hydrodynamic plasma equilibrium solver is described. We use it within the BLUEPRINT reactor design framework to design plasma equilibria and poloidal field coilsets for future fusion reactors in an integrated way. Plasma shape parameters (R-0, A, delta, kappa.) and integral parameters (I-p, beta(p), l(i)) are controlled for. Constrained optimisation procedures for the positions and currents of the poloidal field coils are presented; these account for current, field, force, and positional constraints on the coils. A pulse length constraint is incorporated in the optimisation procedure in the case of pulsed reactors. We demonstrate our approach on three different reactor concepts: single-null, double-null and negative triangularity tokamaks.
引用
收藏
页数:11
相关论文
共 50 条
  • [31] EVALUATION OF ERROR POLOIDAL FIELD IN AN IRON-CORED TOKAMAK
    SOMETANI, T
    MIZUNO, Y
    JAPANESE JOURNAL OF APPLIED PHYSICS PART 1-REGULAR PAPERS SHORT NOTES & REVIEW PAPERS, 1991, 30 (04): : 844 - 847
  • [32] Optimisation of the poloidal field system for advanced divertor configurations in STEP
    Hudoba, A.
    Bakes, S.
    Cunningham, G.
    Henderson, S.
    Eriksson, F.
    Marsden, S.
    Wilson, T.
    NUCLEAR FUSION, 2024, 64 (08)
  • [33] KSTAR poloidal and toroidal field design
    Lee, BJ
    Pomphrey, N
    Chang, CS
    Cho, SY
    Jardin, SC
    Lee, GS
    Neilson, GH
    Park, H
    Reierson, W
    17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2, 1998, : 641 - 644
  • [34] Design of the poloidal field system for KTX
    尤玮
    李弘
    毛文哲
    白伟
    涂翠
    罗兵
    李子超
    阿迪里江
    胡金童
    肖炳甲
    杨庆喜
    谢锦林
    兰涛
    刘阿娣
    丁卫星
    肖持进
    刘万东
    Plasma Science and Technology, 2018, 20 (11) : 130 - 138
  • [35] Upgraded Poloidal Field Control System for HT-7 Tokamak
    王玲
    罗家融
    尹富先
    付鹏
    秦品健
    沈飙
    夏海燕
    王华忠
    刘瑜
    Plasma Science & Technology, 2000, (03) : 311 - 316
  • [36] The electromagnetic geodesic acoustic modes in a tokamak plasma with a poloidal electric field
    Zhou, Deng
    Wang, Jinfang
    Gan, Chenxiao
    PHYSICS OF PLASMAS, 2025, 32 (02)
  • [37] Calculation of the Poloidal Magnetic Field Configuration for the J-TEXT Tokamak
    He, Yong
    Yang, Zhoujun
    Ba, Weigang
    Zhang, Xiaoqing
    Zhuang, Ge
    Hu, Xiwei
    Pan, Yuan
    Liu, Zuli
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2010, 20 (03) : 1840 - 1843
  • [38] ERGODIC BEHAVIOR OF MAGNETIC-FIELD LINES IN A POLOIDAL DIVERTOR TOKAMAK
    YOSHIDA, H
    KISHIMOTO, H
    TAMURA, S
    JAPANESE JOURNAL OF APPLIED PHYSICS PART 1-REGULAR PAPERS SHORT NOTES & REVIEW PAPERS, 1982, 21 (07): : 1068 - 1074
  • [39] DETERMINATION OF OPTIMUM POSITIONS OF POLOIDAL FIELD-COILS OF A LARGE TOKAMAK
    KOBAYASHI, T
    TANI, K
    TAMURA, S
    JAPANESE JOURNAL OF APPLIED PHYSICS, 1978, 17 (12) : 2139 - 2146
  • [40] Discharge and poloidal magnetic field reconstruction in a ferritic first wall tokamak
    Abe, M
    Nakayama, T
    17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2, 1998, : 104 - 107