Effect of divertor geometry on boundary and core plasma performance in ASDEX Upgrade and JET

被引：34
|
作者：
Bosch, HS [1 ]
Fuchs, JC
Gafert, J
Haas, G
Herrmann, A
Kallenbach, A
Kaufmann, M
Neuhauser, J
Ryter, F
Schneider, R
Schweinzer, J
Ullrich, W
Wenzel, U
Vlases, GC
Horton, LD
Matthews, GF
机构：
[1] Max Planck Inst Plasmaphys, IPP, EURATOM Assoc, D-85748 Garching, Germany
[2] Jet Joint Undertaking, Abingdon OX14 3EA, Oxon, England
来源：
PLASMA PHYSICS AND CONTROLLED FUSION | 1999年 / 41卷
关键词：
D O I：
10.1088/0741-3335/41/3A/032
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：
A key element in future toroidal magnetic fusion machines like ITER is the design of a divertor, which allows for safe particle and power exhaust in parallel with high bulk plasma performance. Correspondingly. the definition and design of an optimized divertor is a major task within the ongoing international ITER research and development effort. In order to provide a profound physics basis for such a divertor optimization, different divertor geometries are being tested on major tokamaks. This paper describes the effects of these divertor modifications on plasma performance in ASDEX Upgrade and in JET. In conclusion, increasing closure improves divertor performance without limiting the core plasma performance in ELMy H-modes.
引用
收藏
页码：A401 / A408
页数：8
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