Chapter 2: Plasma confinement and transport
Chapter 2: Plasma confinement and transport
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DOI：
10.1088/0029-5515/39/12/302
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发表时间：
1999
期刊：
影响因子：
3.3
通讯作者：
ITER Physics Expert Group on Confin Transport;ITER Physics Expert Group on Confin Database;ITER Physics Basis Editors-ITER-Physics-Basis-Edito
中科院分区：
文献类型：
--
作者：
ITER Physics Expert Group on Confin Transport;ITER Physics Expert Group on Confin Database;ITER Physics Basis Editors-ITER-Physics-Basis-Edito
回顾了与反应堆规模托卡马克设计相关的等离子体约束和输运物理知识，并提供了将约束特性投影到ITER的方法。本文概述了描述托卡马克中湍流等离子体输运的理论方法，并描述了托卡马克中观察到的主要能量约束机制的现象学，包括边缘和内部输运势垒。本章重点讨论了ITER的基本工作区--高约束区（H模）和边缘局域MHD模的能量约束。目前正在采用三种方法：（一）推导经验性的全球比例律;（二）无量纲的相似研究;（三）一维运输模型代码，建议采用第一种方法，因为它是目前最可靠的方法。特别注意约束预测的不确定性分析。经验标度关系投影L-模式H-模式的功率阈值的基础上回归分析的一个广泛的数据库进行了讨论。评述了粒子和环向动量约束及其与能量约束的关系。
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.