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Development of a thermo-hydraulic bypass leakage test method for the Wendelstein 7-X target element cooling structure

MPS-Authors
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Smirnow,  M.
Tokamak Scenario Development (E1), Max Planck Institute for Plasma Physics, Max Planck Society;

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Drescher,  N.
Tokamak Scenario Development (E1), Max Planck Institute for Plasma Physics, Max Planck Society;

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Höschen,  T.
Material Research (MF), Max Planck Institute for Plasma Physics, Max Planck Society;

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

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

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Tivey,  R.
Max Planck Institute for Plasma Physics, Max Planck Society;

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Citation

Smirnow, M., Drescher, N., Höschen, T., Peacock, A., Boscary, J., & Tivey, R. (2010). Development of a thermo-hydraulic bypass leakage test method for the Wendelstein 7-X target element cooling structure. Poster presented at 26th Symposium on Fusion Technology (SOFT 2010), Porto.


Cite as: http://hdl.handle.net/21.11116/0000-0000-5472-1
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