Divertor regimes in NSTX-Reference-Cited by-同舟云学术

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Divertor regimes in NSTX

Published:2005-03 Issue: Volume:337-339 Page:475-479
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Soukhanovskii V.A.,Maingi R.,Roquemore A.L.,Boedo J.,Bush C.,Kaita R.,Kugel H.W.,LeBlanc B.P.,Paul S.F.,Porter G.D.,Wolf N.S.

Publisher

Elsevier BV

Subject

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

Reference23 articles.

1. The plasma boundary of Magnetic Fusion Devices;Stangeby,2000

2. Parallel SOL transport in MAST and JET: the impact of the mirror force

3. Exhaust, ELM, and halo physics using the MAST tokamak

4. Effect of gas fuelling location on H-mode access in NSTX

5. Heat flux scaling experiments in NSTX

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1. Configuration characteristics of the Chinese First Quasi-axisymmetric Stellarator;Nuclear Fusion;2020-11-24

2. Investigation of the dependency of JET midplane separatrix density as a function of engineering parameters;Contributions to Plasma Physics;2020-04-19

3. Drift effects on W7-X divertor heat and particle fluxes;Plasma Physics and Controlled Fusion;2019-10-23

4. Supersonic Gas Injector for Plasma Fueling in the National Spherical Torus Experiment;Fusion Science and Technology;2018-10

5. A review of radiative detachment studies in tokamak advanced magnetic divertor configurations;Plasma Physics and Controlled Fusion;2017-04-28

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