Self-consistent plasma-neutral modeling in tokamak plasmas with a large-area toroidal belt limiter

被引:13
|
作者
Gray, DS [1 ]
Baelmans, M
Boedo, JA
Reiter, D
Conn, RW
机构
[1] Univ Calif San Diego, Dept Appl Mech & Engn Sci, La Jolla, CA 92093 USA
[2] Forschungszentrum Juclich GmbH, Inst Plasma Phys, Julich, Germany
关键词
D O I
10.1063/1.873239
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Plasma-neutral phenomena in the edge plasma and scrape-off layer of the Torus Experiment for Technology Oriented Research [G.H. Wolf and the TEXTOR Team, J. Nucl. Mater. 122&123, 1124 (1984)] with the toroidal belt Advanced Limiter Test (ALT-II) [D.M. Goebel et al;, J. Nucl. Mater. 162-164, 115 (1989)] are simulated using the code package B2-EIRENE [D. Reiter et al;, Plasma Phys. Controlled Fusion 33, 1579 (1991)]. Spatially-constant, anomalous radial transport coefficients (D,V,chi) are used for fitting measured electron temperature and density profiles. Primary neutral fluxes are determined by plasma fluxes to material surfaces, and D alpha emissions are predicted from them. Comparison of the predicted D alpha emission with measurements indicates a critical need, in predictive modeling, for a self-consistent model of fluxes to material surfaces that are parallel to the magnetic field. Appropriate factors are calculated for deducing D+ source rates from D alpha emissions measured in various locations, taking into account molecular processes and spatially varying plasma parameters; values range from 17 to 28 ions/photon. Ion fluxes lost to pumps or the wall must be explicitly re-introduced as neutral fluxes at the outer boundary. (C) 1999 American Institute of Physics. [S1070-664X(99)03707-6].
引用
收藏
页码:2816 / 2825
页数:10
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