Heat flux scaling experiments in NSTX-Reference-Cited by-同舟云学术

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Heat flux scaling experiments in NSTX

Published:2003-03 Issue: Volume:313-316 Page:1005-1009
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Maingi R.,Kugel H.W.,Lasnier C.J.,Roquemore A.L.,Soukhanovskii V.A.,Bush C.E.,The NSTX Team

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference12 articles.

1. High-performance discharges in the Small Tight Aspect Ratio Tokamak (START)

2. Achievement of Recordβin the START Spherical Tokamak

3. Beta-limiting instabilities and global mode stabilization in the National Spherical Torus Experiment

4. Experimental investigations of the SOL plasma in the MAST tokamak

5. Exploration of spherical torus physics in the NSTX device

Cited by 8 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Recent progress on spherical torus research;Physics of Plasmas;2015-04

2. Temperature Distribution and Heat Flux on the EAST Divertor Targets in H-Mode;Plasma Science and Technology;2013-03

3. Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX;Journal of Nuclear Materials;2011-08

4. Divertor heat flux mitigation in high-performance H-mode discharges in the National Spherical Torus Experiment;Nuclear Fusion;2009-09

5. Divertor heat flux mitigation in the National Spherical Torus Experiment;Physics of Plasmas;2009-02

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