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

机译:具有大面积环形带限制器的托卡马克等离子体中的自洽等离子体中性建模

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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]. [References: 20]
机译:面向技术的Torus实验的边缘等离子体和刮除层中的等离子体中性现象[G.H.沃尔夫和TEXTOR团队,J。Nucl。母校122&123,1124(1984)],并使用环形带Advanced Limiter Test(ALT-II)[D.M. Goebel et al;,J.Nucl.Chem.Soc。,1993,48,1959。母校162-164,115(1989)]使用代码包B2-EIRENE [D. Reiter等;等离子物理学。 Controlled Fusion 33,1579(1991)]。使用空间常数的异常径向传输系数(D,V,chi)来拟合测得的电子温度和密度曲线。初级中性通量由到材料表面的等离子体通量确定,并据此预测D alpha发射。预测的D alpha发射量与测量值的比较表明,在预测建模中,迫切需要对与磁场平行的材料表面通量的自洽模型。考虑到分子过程和空间变化的等离子体参数,计算适当的因子以从在不同位置测得的D alpha排放量推导出D +源速率。值范围从17到28个离子/光子。输给泵或壁的离子通量必须明确地重新引入为外边界处的中性通量。 (C)1999美国物理研究所。 [S1070-664X(99)03707-6]。 [参考:20]

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