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

Smirnow, M.; Drescher, N.; Höschen, T.; Peacock, A.; Boscary, J.; Tivey, R.

doi:10.1016/j.fusengdes.2011.04.042

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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;

/persons/resource/persons108974

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

/persons/resource/persons109412

Höschen, T.
Material Research (MF), Max Planck Institute for Plasma Physics, Max Planck Society;
Plasma Edge and Wall (E2M), Max Planck Institute for Plasma Physics, Max Planck Society;

/persons/resource/persons110119

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;

/persons/resource/persons108756

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;

/persons/resource/persons110648

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

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Smirnow, M., Drescher, N., Höschen, T., Peacock, A., Boscary, J., & Tivey, R. (2011). Development of a thermo-hydraulic bypass leakage test method for the Wendelstein 7-X target element cooling structure. Fusion Engineering and Design, 86(9-11), 1732-1735. doi:10.1016/j.fusengdes.2011.04.042.

Cite as: https://hdl.handle.net/11858/00-001M-0000-0026-E99E-D

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