Impurity transport studies in NSTX neutral beam heated H-mode plasmas-Reference-Cited by-同舟云学术

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Impurity transport studies in NSTX neutral beam heated H-mode plasmas

Published:2009-07-22 Issue:8 Volume:49 Page:085028
ISSN:0029-5515
Container-title:Nuclear Fusion
language:
Short-container-title:Nucl. Fusion

Author:

Delgado-Aparicio L.,Stutman D.,Tritz K.,Finkenthal M.,Kaye S.,Bell R.,Kaita R.,LeBlanc B.,Levinton F.,Menard J.,Paul S.,Smith D.,Yuh H.

Publisher

IOP Publishing

Subject

Condensed Matter Physics,Nuclear and High Energy Physics

Reference31 articles.

1. Exploration of spherical torus physics in the NSTX device

2. Ideal MHD stability limits of low aspect ratio tokamak plasmas

3. Physics basis for a spherical torus power plant

4. A component test facility based on the spherical tokamak

5. Impurity transport measurements in beam heated low-confinement mode discharges in the National Spherical Torus Experiment

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1. Experimental inference of neutral and impurity transport in Alcator C-Mod using high-resolution x-ray and ultra-violet spectra;Nuclear Fusion;2021-11-18

2. Inference of experimental radial impurity transport on Alcator C-Mod: Bayesian parameter estimation and model selection;Nuclear Fusion;2020-10-02

3. Prospects of X-ray imaging spectrometers for impurity transport: Recent results from the stellarator Wendelstein 7-X (invited);Review of Scientific Instruments;2018-10

4. Parametric dependencies of the experimental tungsten transport coefficients in ICRH and ECRH assisted ASDEX Upgrade H-modes;Physics of Plasmas;2017-11

5. Analysis of electron temperature, impurity transport and MHD activity with multi-energy soft x-ray diagnostic in EAST tokamak;Plasma Science and Technology;2017-10-23

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