Compatibility of H-mode with a radiating boundary and divertor detachment

被引：5
|
作者：
Bosch, HS [1 ]
Gruber, O [1 ]
Haas, G [1 ]
Kallenbach, A [1 ]
Kaufmann, M [1 ]
Lackner, K [1 ]
Mertens, V [1 ]
Neu, R [1 ]
Neuhauser, J [1 ]
Ryter, F [1 ]
Schweinzer, J [1 ]
Zohm, H [1 ]
机构：
[1] EURATOM, MAX PLANCK INST PLASMAPHYS, IPP ASSOC, BERLIN, GERMANY
来源：
PLASMA PHYSICS AND CONTROLLED FUSION | 1996年 / 38卷 / 08期
关键词：
D O I：
10.1088/0741-3335/38/8/061
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 or any other future fusion device will operate in H-mode to take advantage of the improved confinement. Stationary operation in H-mode, however, requires the occurrence of ELMs, and the resulting power load on the divertor target plates is not acceptable from the engineering point of view. Beyond this, the present divertor concepts rely on a cold and dense (possibly detached) divertor plasma. Large type-I ELMs, however, carry tao large a power and possibly burn through such cold divertor plasmas. The completely detached I-I-mode (CDH-mode), recently established in ASDEX Upgrade shows detachment at both divertor target plates and small ELMs (so-called type-III ELMs), that do not burn through the divertor plasma. The extrapolation of this scenario to ITER, however, is an important question.
引用
收藏
页码：1493 / 1496
页数：4
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