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Instrumentation and Analysis of the W7-X Inertially Cooled Test Divertor Unit Scraper Element Design

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Boscary,  J.
Tokamak Scenario Development (E1), Max Planck Institute for Plasma Physics, Max Planck Society;
W7-X: In-vessel Components (KIP), Max Planck Institute for Plasma Physics, Max Planck Society;

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Fellinger,  J.
W7-X: Engineering (EN), Max Planck Institute for Plasma Physics, Max Planck Society;

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Hölbe,  H.
Stellarator Edge and Divertor Physics (E4), Max Planck Institute for Plasma Physics, Max Planck Society;

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König,  R.
W7-X: Diagnostics (DIA), Max Planck Institute for Plasma Physics, Max Planck Society;

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Peacock,  A.
Tokamak Scenario Development (E1), Max Planck Institute for Plasma Physics, Max Planck Society;
W7-X: In-vessel Components (KIP), Max Planck Institute for Plasma Physics, Max Planck Society;

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Tretter,  J.
Integrated Technic Center (ITZ), Max Planck Institute for Plasma Physics, Max Planck Society;

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Citation

Lumsdaine, A., Boscary, J., Fellinger, J., Harris, J., Hölbe, H., König, R., et al. (2014). Instrumentation and Analysis of the W7-X Inertially Cooled Test Divertor Unit Scraper Element Design. Poster presented at 21st Topical Meeting on the Technology of Fusion Energy (TOFE), Anaheim, CA.


Cite as: https://hdl.handle.net/11858/00-001M-0000-0024-3525-C
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