托卡马克
等离子体约束
物理
磁聚变
缩放比例
等离子体
环面
湍流
磁流体力学
现象学(哲学)
统计物理学
计算物理学
核物理学
机械
哲学
几何学
数学
认识论
作者
ITER Physics Expert Group on Confin Transport,ITER Physics Expert Group on Confin Database,ITER Physics Basis Editors
出处
期刊:Nuclear Fusion
[IOP Publishing]
日期:1999-12-01
卷期号:39 (12): 2175-2249
被引量:887
标识
DOI:10.1088/0029-5515/39/12/302
摘要
Physics knowledge in plasma confinement and transport relevant to design of a reactor-scale tokamak is reviewed and methodologies for projecting confinement properties to ITER are provided. Theoretical approaches to describing a turbulent plasma transport in a tokamak are outlined and phenomenology of major energy confinement regimes observed in tokamaks, including those with edge and internal transport barriers, is described. The chapter is focused on the energy confinement in the high confinement regime (H-mode) with the edge localized MHD modes, the basic operational regime of ITER. Three approaches are being pursued: (i) derivation of empirical global scaling laws; (ii) non-dimensionally similar studies; and (iii) one dimensional transport modelling codes, with the first approach recommended as the most robust at the present time. Special attention is paid to analysis of uncertainties in confinement predictions. Empirical scaling relations for projecting the L-mode to H-mode power threshold based on regression analysis of an extensive database are discussed. Particle and toroidal momentum confinement and their relation to energy confinement are reviewed.
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