On the W7-X divertor performance under detached conditions

被引：35
|
作者：
Feng, Y. [1 ]
Beidler, C. D. [1 ]
Geiger, J. [1 ]
Helander, P. [1 ]
Hoelbe, H. [1 ]
Maassberg, H. [1 ]
Turkin, Y. [1 ]
Reiter, D. [2 ]
机构：
[1] Max Planck Inst Plasma Phys, D-17491 Greifswald, Germany
[2] Forschungszentrum Julich, Inst Energie & Klimaforsch Plasmaphys, D-52425 Julich, Germany
来源：
NUCLEAR FUSION | 2016年 / 56卷 / 12期
关键词：
island divertor; modeling; impurity radiation; detachment; ISLAND DIVERTOR; EDGE PLASMA; STELLARATOR; TRANSPORT; PHYSICS; MARFE;
D O I：
10.1088/0029-5515/56/12/126011
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：
We present a theoretical/numerical predictive analysis of the performance of the W7-X island divertor under conditions of detachment characterized by intensive radiation. The analysis is based on EMC3-Eirene simulations and the earlier W7-AS experimental and numerical experience. Carbon is employed as a representative radiator. The associated drawbacks, i.e. core contamination and recycling degradation (reduced recycling flux), are evaluated by determining the carbon density at the last closed flux surface (LCFS) and the neutral pressure in the divertor chamber. Optimum conditions are explored in both configuration and plasma parameter space. This study aims to identify the key geometric/magnetic and plasma parameters that affect the performance of detached plasmas in W7-X. Emphasis is placed on what occurs when the islands are enlarged far beyond the maximum size available in W7-AS and whether an island size limit for optimal detachment operation exists, and why. Further issues addressed are the power removal ability of the W7-X edge islands, potentially limiting factors, compatibility between particle and power exhaust, and particle refueling capability of the recycling neutrals.
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页数：13
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