Heat flux scaling experiments in NSTX

被引:8
作者
Maingi, R [1 ]
Kugel, HW [1 ]
Lasnier, CJ [1 ]
Roquemore, AL [1 ]
Soukhanovskii, VA [1 ]
Bush, CE [1 ]
机构
[1] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
关键词
plasma-wall interactions; divertor; boundary plasmas; heat flux; power balance; infrared thermogrpaphy;
D O I
10.1016/S0022-3115(02)01441-1
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
We report the first results of heat flux scaling experiments in National Spherical Torus Experiment (NSTX). We find that the peak heat flux observed in the outer divertor was similar to6 MW/m(2) at 5 MW heating power in lower-single-null diverted configuration. The peak heat flux was observed to increase with heating power, and the highest heat fluxes had narrow profile widths. The peak heat flux is lower than predicted by early 2-D edge transport conservative design calculations. However, the total power flow to the divertor is only 15-30% of the input power, suggesting other processes reduce the available open field line power which can be conducted and convected to the target. (C) 2003 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:1005 / 1009
页数:5
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