کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1569177 1514257 2007 5 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Divertor heat flux scaling with heating power and plasma current in H-mode discharges in the national spherical torus experiment
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
Divertor heat flux scaling with heating power and plasma current in H-mode discharges in the national spherical torus experiment
چکیده انگلیسی

We present the first results of lower divertor heat flux scaling with input power (PNBI) and plasma current (Ip) in H-mode discharges in the National Spherical Torus Experiment. These experiments were conducted with 0.6 ⩽ Ip ⩽ 0.9 MA, 1 < PNBI < 6 MW, on-axis toroidal field Bt = 0.45 T, in a lower-single null discharge shape with elongation κ ∼ 2.0, triangularity δ ∼ 0.45, and the ion grad-B drift toward the X-point. As PNBI was raised from 1 MW to 6 MW, the outer divertor peak heat flux was observed to increase up to 6 MW/m2. A break in the slope of peak heat flux vs. power was observed at heating power ∼3 MW, which we interpret as the transition of the divertor toward the high recycling regime and well away from the detachment threshold. The peak heat flux was also observed to increase strongly with Ip.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volumes 363–365, 15 June 2007, Pages 196–200
نویسندگان
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