Dependence of SOL widths on plasma current and density in NSTX H-mode plasmas
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. Multi-machine scaling of the divertor peak heat flux and width for L-mode and H-mode discharges
2. Boundary plasma energy transport in JET ELMy H-modes
3. ITER edge database investigations of the SOL width
4. L-mode SOL width scaling in the MAST spherical tokamak
5. Divertor heat flux scaling with heating power and plasma current in H-mode discharges in the national spherical torus experiment
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1. Experimental investigation of free and bounded presheaths in weakly magnetized plasmas;Current Applied Physics;2017-03
2. L-mode filament characteristics on MAST as a function of plasma current measured using visible imaging;Plasma Physics and Controlled Fusion;2016-07-15
3. Parallel heat flux and flow acceleration in open field line plasmas with magnetic trapping;Physics of Plasmas;2014-10
4. Heat-flux footprints for I-mode and EDA H-mode plasmas on Alcator C-Mod;Journal of Nuclear Materials;2013-07
5. Concept of the divertor of a fusion neutron source based on a spherical tokamak;Plasma Physics Reports;2012-07
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