Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion

被引：27
|
作者：
Brooks, J. N. [1 ]
Elder, J. D. [2 ]
McLean, A. G. [3 ]
Rudakov, D. L. [4 ]
Stangeby, P. C. [2 ]
Wampler, W. R. [5 ]
机构：
[1] Purdue Univ, W Lafayette, IN 47907 USA
[2] Univ Toronto, Inst Aerosp Studies, Toronto, ON, Canada
[3] Lawrence Livermore Natl Lab, Livermore, CA USA
[4] Univ Calif San Diego, San Diego, CA 92103 USA
[5] Sandia Natl Labs, Albuquerque, NM 87185 USA
来源：
FUSION ENGINEERING AND DESIGN | 2015年 / 94卷
关键词：
Sputtering; Erosion/redeposition; Tungsten divertor; Plasma material interaction modeling; DIVERTOR;
D O I：
10.1016/j.fusengdes.2015.03.022
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：
We analyze a DIII-D tokamak experiment where two tungsten spots on the removable DiMES divertor probe were exposed to 12 s of attached plasma conditions, with moderate strike point temperature and density (similar to 20 eV, similar to 4.5 x 10(19) m(-3)), and 3% carbon impurity content. Both very small (1 mm diameter) and small (I cm diameter) deposited samples were used for assessing gross and net tungsten sputtering erosion. The analysis uses a 3-D erosion/redeposition code package (REDEP/WBC), with input from a diagnostic-calibrated near-surface plasma code (OEDGE), and with focus on charge state resolved impinging carbon ion flux and energy. The tungsten surfaces are primarily sputtered by the carbon, in charge states +1 10 +4. We predict high redeposition (similar to 75%) of sputtered tungsten on the 1 cm spot with consequent reduced net erosion and this agrees well with post-exposure DiMES probe RBS analysis data. This study and recent related work is encouraging for erosion lifetime and non-contamination performance of tokamak reactor high-Z plasma facing components. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码：67 / 71
页数：5
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