Inferring the scrape-off layer heat flux width in a divertor with a low degree of axisymmetry

被引:2
|
作者
Marsden, C. [1 ]
Zhang, X. [1 ]
Moscheni, M. [1 ]
Gray, T. K. [2 ]
Vekshina, E. [1 ]
Rengle, A. [1 ]
Scarabosio, A. [3 ]
Sertoli, M. [1 ]
Romanelli, M. [1 ]
机构
[1] Tokamak Energy Ltd, 173 Brook Dr,Milton Pk, Abingdon, England
[2] Oak Ridge Natl Lab, Fus Energy Div, Oak Ridge, TN USA
[3] LINKS Fdn, Via Pier Carlo Boggio 61, I-10138 Turin, Italy
关键词
Divertor; Scrape-off layer; Infrared thermography; Spherical Tokamak;
D O I
10.1016/j.nme.2024.101773
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
Plasma facing components (PFCs) in the next generation of tokamak devices will operate in challenging environments, with heat loads predicted to exceed 10 MW/m2. The magnitude of these heat loads is set by the width of the channel, the 'scrape-off layer' (SOL), into which heat is exhausted, and can be characterised by an e-folding length scale for the decay of heat flux across the channel. It is expected this channel will narrow as tokamaks move towards reactor relevant conditions. Understanding the processes involved in setting the SOL heat flux width is imperative to be able to predict the heat loads PFCs must handle in future devices. Measurements of the SOL width are performed on the high-field spherical tokamak, ST40, using a newly commissioned infrared thermography system. With its high on-axis toroidal magnetic field (>= 1.5 T) ST40 is uniquely positioned to investigate the influence of toroidal field on the heat flux width in spherical tokamaks, whilst also extending measurements of the SOL width in spherical tokamaks to increased poloidal field (>= 0.3 T). Due to the divertor on ST40 having a low degree of axisymmetry, it is necessary for a set of radial measurements of the heat flux to betaken across the divertor, made possible using an automated toolchain that fully incorporates its 3D geometry. These radial profiles are combined with the magnetic geometry of the plasma to infer the width of the SOL, with both Eich and double exponential profiles of heat flux observed. A reduction in the heat flux is observed toroidally across part of the divertor, along with increased heat loads observed locally around the edges of the tiles. Future work in characterising the impact of tile misalignment and uncertainties in the reconstructed divertor magnetic geometry is required in order to further understand the observed heat flux patterns, as are additional investigations into the role potentially being played by an inhomogeneous sheath electric field.
引用
收藏
页数:6
相关论文
共 50 条
  • [41] CHARACTERISTICS OF DIVERTOR PLASMA AND SCRAPE-OFF LAYER IN JT-60U
    ITAMI, K
    SHIMADA, M
    HOSOGANE, N
    JOURNAL OF NUCLEAR MATERIALS, 1992, 196 : 755 - 758
  • [42] Understanding and suppressing the near scrape-off layer heat flux feature in inboardlimited plasmas in TCV
    Nespoli, F.
    Labit, B.
    Furno, I.
    Horacek, J.
    Tsui, C. K.
    Boedo, J. A.
    Maurizio, R.
    Reimerdes, H.
    Theiler, C.
    Ricci, P.
    Halpern, F. D.
    Sheikh, U.
    Verhaegh, K.
    Pitts, R. A.
    Militello, F.
    NUCLEAR FUSION, 2017, 57 (12)
  • [43] Divertor asymmetry and scrape-off layer flow in various divertor configurations in Experimental Advanced Superconducting Tokamak
    Liu, S. C.
    Guo, H. Y.
    Xu, G. S.
    Gao, X.
    Zhu, S. Z.
    Wang, H. Q.
    Wang, L.
    Yan, N.
    Wang, D. S.
    Liu, P.
    Jiang, M.
    Zhang, W.
    Ming, T. F.
    Chang, J. F.
    Ding, S. Y.
    Xiong, H.
    Shao, L. M.
    Wu, Z. W.
    Luo, G. N.
    PHYSICS OF PLASMAS, 2012, 19 (04)
  • [44] FLUID THEORY OF DIVERTOR AND LIMITER SCRAPE-OFF LAYERS
    BOOZER, AH
    BULLETIN OF THE AMERICAN PHYSICAL SOCIETY, 1977, 22 (09): : 1106 - 1106
  • [45] A theoretical interpretation of the main scrape-off layer heat-flux width scaling for tokamak inner-wall limited plasmas
    Halpern, F. D.
    Horacek, J.
    Pitts, R. A.
    Ricci, P.
    PLASMA PHYSICS AND CONTROLLED FUSION, 2016, 58 (08)
  • [46] On the role of filaments in perpendicular heat transport at the scrape-off layer
    Carralero, D.
    Artene, S.
    Bernert, M.
    Birkenmeier, G.
    Faitsch, M.
    Manz, P.
    de Marne, P.
    Stroth, U.
    Wischmeier, M.
    Wolfrum, E.
    NUCLEAR FUSION, 2018, 58 (09)
  • [47] Scrape-off layer heat transport and divertor power deposition of pellet-induced edge localized modes
    Wenninger, R. P.
    Eich, T. H.
    Huysmans, G. T. A.
    Lang, P. T.
    Devaux, S.
    Jachmich, S.
    Koechl, F.
    PLASMA PHYSICS AND CONTROLLED FUSION, 2011, 53 (10)
  • [48] Scrape-off layer power flux measurements in the Tore Supra tokamak
    Gunn, J. P.
    Dejarnac, R.
    Devynck, P.
    Fedorczak, N.
    Fuchs, V.
    Gil, C.
    Kocan, M.
    Komm, M.
    Kubic, M.
    Lunt, T.
    Monier-Garbet, P.
    Pascal, J. -Y.
    St Laurent, F.
    JOURNAL OF NUCLEAR MATERIALS, 2013, 438 : S184 - S188
  • [49] Far ultraviolet polychromator for spectroscopic characterization of the tokamak divertor and plasma scrape-off layer
    Soukhanovskii, VA
    Stutman, D
    May, MJ
    Finkenthal, M
    Moos, HW
    Terry, JL
    Goetz, JA
    Lipschultz, B
    REVIEW OF SCIENTIFIC INSTRUMENTS, 1999, 70 (01): : 340 - 343
  • [50] TWO-DIMENSIONAL ANALYSIS OF LIMITER DIVERTOR TRANSITION IN SCRAPE-OFF LAYER PLASMAS
    UEDA, N
    ITOH, K
    ITOH, SI
    NUCLEAR FUSION, 1989, 29 (02) : 173 - 184