ITER: opportunity of burning plasma studies

被引:61
作者
Shimomura, Y
Murakami, Y
Polevoi, AR
Barabaschi, P
Mukhovatov, V
Shimada, M
机构
[1] ITER, Joint Cent Team, Naka, Ibaraki, Japan
[2] ITER, Joint Cent Team, Naka, Ibaraki, Japan
关键词
D O I
10.1088/0741-3335/43/12A/329
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
ITER is planned to be the first fusion experiment operating under reactor-relevant conditions. The following requirements are given: ITER should (1) achieve extended burn in inductively driven plasma at Q greater than or equal to 10, whilst not precluding the possibility of controlled ignition, (2) aim at demonstrating steady-state operation using non-inductive current drive at Q greater than or equal to 5, (3) demonstrate availability and integration of essential fusion technologies, and (4) test components for a future reactor including tritium breeding module concepts, with the 14 MeV neutron power load on the first wall greater than or equal to 0.5 MW m(-2) and fluence greater than or equal to 0.3 MW am(-2). The ITER tokamak is designed not only to satisfy these requirements but also to have flexibility of plasma operations. This flexibility will provide a wide range of opportunities to develop inductive and non-inductive reactor core plasmas and to study burning plasma physics. Possible operational modes studying physics and technical issues of burning plasmas are overviewed.
引用
收藏
页码:A385 / A394
页数:10
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