Progress with heating and current drive technologies

被引:3
|
作者
Robinson, DC [1 ]
Cox, M [1 ]
Lloyd, B [1 ]
Nightingale, M [1 ]
机构
[1] UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
基金
欧盟地平线“2020”;
关键词
heating; current drive; power plants;
D O I
10.1016/S0920-3796(99)00028-9
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
High power heating and current drive (H&CD) facilities are required to fulfil a number of functions in Next Step tokamaks such as ITER and in power plants. The main functions of the ITER H&CD systems are: start-up assist; H-mode access; heating to ignition; supplementary heating for driven-burn and for controlled plasma shut-down; current drive for extended burn and access to steady-state regimes; performance optimisation, control of plasma instabilities and making the plasma rotate. This paper reviews recent progress with H&CD systems, which has largely come about in response to the needs of ITER [1-3]. We survey how the designs have been influenced by physics requirements and technical constraints (such as reliable c.w. operation with modular integrated port plug designs), and emphasise key outstanding issues. The four main candidate systems are: electron and ion cyclotron resonance frequency, lower hybrid, and neutral beam heating. These all have their own physics and technology advantages, and disadvantages, and their components are at various stages of development. (C) 1999 UKAEA Fusion. Published by Elsevier Science S.A. All rights reserved.
引用
收藏
页码:355 / 369
页数:15
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