Development of an advanced magnetic equilibrium model for fusion reactor system codes

被引:4
|
作者
Franza, F. [1 ]
Landman, I. S. [1 ]
Pestchanyi, S. [1 ]
机构
[1] Karlsruhe Inst Technol, Hermann von Helmholtz Pl 1, D-76344 Eggenstein Leopoldshafen, Germany
关键词
System codes; DEMO; Magnets; Equilibrium;
D O I
10.1016/j.fusengdes.2018.02.014
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
Fusion system codes are vital computational tools for the assessment of the key design parameters of a fusion power plant. The main goal is to capture the key physics and technology aspects, pushing the solution to comply with physics and engineering requirements and constraints. Based on that, the magnet system has to be designed to match the requirements on magnetic equilibrium as well as the technological constraints on superconductive coils. A dedicated model was developed to evaluate the coupling effects between the external poloidal field coils (PFCs) and the plasma, described in terms of its magnetic equilibrium configuration. The model first attempts to reproduce a magnetic configuration for a given set of plasma parameters within a target confining region. To achieve such an arrangement, a coil solver calculates the toroidal electrical currents in PFCs. In this paper, the mathematical details of this equilibrium model are presented and the main results referred to magnetic flux, field and coil currents are compared to a reference DEMO scenario calculation.
引用
收藏
页码:309 / 313
页数:5
相关论文
共 50 条
  • [21] Research and development of the tritium recovery system for the blanket of the fusion reactor in JAEA
    Kawamura, Y.
    Isobe, K.
    Iwai, Y.
    Kobayashi, K.
    Nakamura, H.
    Hayashi, T.
    Yamanishi, T.
    [J]. NUCLEAR FUSION, 2009, 49 (05)
  • [22] MHD EQUILIBRIUM PROPERTIES OF TOKAMAK FUSION REACTOR DESIGNS
    TODD, AMM
    GRALNICK, SL
    DALHED, HE
    [J]. NUCLEAR FUSION, 1976, 16 (04) : 687 - 689
  • [23] Research and development of the tritium recovery system for the blanket of the fusion reactor in JAEA
    Japan Atomic Energy Agency, 2-4 Shirane Shirakata, Tokai, Ibaraki, 319-1195, Japan
    [J]. Nucl Fusion, 1600, 5
  • [24] Advanced welding processes for fusion reactor fabrication
    Sanderson, A
    Punshon, CS
    Russell, JD
    [J]. FUSION ENGINEERING AND DESIGN, 2000, 49-50 : 77 - 87
  • [25] APPLICATION OF PARTICLE SIMULATION CODES TO FUSION-REACTOR ENGINEERING
    MORSE, EC
    DROBOT, A
    FRIEDMAN, A
    MCNAMARA, B
    [J]. NUCLEAR TECHNOLOGY-FUSION, 1983, 3 (02): : 287 - 292
  • [26] APPLICATIONS OF PARTICLE SIMULATION CODES TO FUSION-REACTOR ENGINEERING
    MORSE, EC
    DROBOT, A
    FRIEDMAN, A
    MCNAMARA, B
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 41 : 325 - 326
  • [27] On the implementation of new technology modules for fusion reactor systems codes
    Franza, F.
    Boccaccini, L. V.
    Fisher, U.
    Gade, P. V.
    Heller, R.
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1767 - 1770
  • [28] Advanced reactor development rebounding
    Sweet, W
    [J]. IEEE SPECTRUM, 1997, 34 (11) : 41 - 48
  • [29] ADVANCED REACTOR DEVELOPMENT IN JAPAN
    SAWAI, S
    MOCHIZUKI, K
    TAKETANI, K
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 29 (SEP): : 329 - 334
  • [30] Tritium control in fusion reactor materials: A model for Tritium Extracting System
    Zucchetti, Massimo
    Utili, Marco
    Nicolotti, Iuri
    Ying, Alice
    Franza, Fabrizio
    Abdou, Mohamed
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1885 - 1888