کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
10645121 | 999835 | 2011 | 5 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX
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موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
انرژی هسته ای و مهندسی
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چکیده انگلیسی
We report the dependence of the lower divertor surface heat flux profiles, measured from infrared thermography and mapped magnetically to the mid-plane on loss power into the scrape-off layer (PLOSS), plasma current (Ip), and magnetic flux expansion (fexp), as well as initial results with lithium wall conditioning in NSTX. Here we extend previous studies [R. Maingi et al., J. Nucl. Mater. 363-365 (2007) 196-200] to higher triangularity â¼0.7 and higher Ip ⩽ 1.2 MA. First we note that the mid-plane heat flux width mapped to the mid-plane, λqmid, is largely independent of PLOSS for PLOSS ⩾ 4 MW. λqmid is also found to be relatively independent of fexp; peak heat flux is strongly reduced as fexp is increased, as expected. Finally, λqmid is shown to strongly contract with increasing Ip such that λqmidâIp-1.6 with a peak divertor heat flux of qdiv, peak â¼Â 15 MW/m2 when Ip = 1.2 MA and PLOSS â¼Â 6 MW. These relationships are then used to predict the divertor heat flux for the planned NSTX-Upgrade, with heating power between 10 and 15 MW, Bt = 1.0 T and Ip = 2.0 MA for 5 s.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 415, Issue 1, Supplement, 1 August 2011, Pages S360-S364
Journal: Journal of Nuclear Materials - Volume 415, Issue 1, Supplement, 1 August 2011, Pages S360-S364
نویسندگان
T.K. Gray, R. Maingi, V.A. Soukhanovskii, J.E. Surany, J.-W. Ahn, A.G. McLean,