Wall conditioning throughout the first carbon divertor campaign on Wendelstein 7-X
Author:
Funder
EURATOM
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics
Reference19 articles.
1. EPS Conference on Plasma Physics July 4;Wolf,2018
2. Progress in the design and development of a test divertor (TDU) for the start of W7-X operation;Peacock;Fusion Eng. Des.,2009
3. Design and technological solutions for the plasma facing components of WENDELSTEIN 7-X;Boscary;Fusion Eng. Des.,2011
4. Electron Cyclotron Heating for W7-X: Physics and Technology
5. Neutral particle modelling and particle exhaust in the Wendelstein 7-X stellarator
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2. Plasma–surface interaction in the stellarator W7-X: conclusions drawn from operation with graphite plasma-facing components;Nuclear Fusion;2021-12-02
3. Ion temperature clamping in Wendelstein 7-X electron cyclotron heated plasmas;Nuclear Fusion;2021-10-25
4. Overview of the results from divertor experiments with attached and detached plasmas at Wendelstein 7-X and their implications for steady-state operation;Nuclear Fusion;2021-08-30
5. Removal of tritium from vacuum vessel by RF heated plasmas in LHD;Physica Scripta;2021-08-17
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