Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device

被引：0
|
作者：
Shoji, M. [1 ,2 ]
Kawamura, G. [1 ,2 ]
Romazanov, J. [3 ]
Kirschner, A. [3 ]
Masuzaki, S. [1 ,2 ]
Tokitani, M. [1 ,2 ]
Brezinsek, S. [3 ]
机构：
[1] Natl Inst Nat Sci, Natl Inst Fus Sci, 322-6 Oroshi Cho, Toki, Gifu 5095292, Japan
[2] Grad Univ Adv Studies SOKENDAI, Hayama, Kanagawa 2400913, Japan
[3] Forschungszentrum Julich, Trilateral Euregio Cluster TEC, Inst Energie & Klimaforsch Plasmaphys, D-52425 Julich, Germany
来源：
NUCLEAR MATERIALS AND ENERGY | 2022年 / 33卷
关键词：
ERO2; 0; Tungsten migration; Plasma -wall interaction; EMC3-EIRENE; LHD; EROSION;
D O I：
10.1016/j.nme.2022.101257
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：
Tungsten migration in the open divertor region in the Large Helical Device is analyzed for validating the three-dimensional plasma-wall interaction simulation code ERO2.0. The ERO2.0 simulation reproduced the mea-surement of localized tungsten migration from a tungsten-coated divertor plate installed in the inboard side of the torus. The simulation also explained the measurement of the high tungsten areal density in the private side on a carbon divertor plate, next to the tungsten-coated divertor plate, by the tungsten prompt redeposition in plasma discharges for a low magnetic field strength in a counterclockwise toroidal direction. However, the simulation disagreed with the measurement of low tungsten areal density on the plasma-wetted areas on the carbon divertor plates, which indicated that the actual erosion rate of the redeposited tungsten should be much higher than that used in the ERO2.0 code.
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页数：7
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