Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
9793824 | Journal of Nuclear Materials | 2005 | 5 Pages |
Abstract
In order to prepare for tungsten coating to be applied to the low field side poloidal guard limiters, 1 μm W-coated CFC limiter tests have been performed in ASDEX Upgrade. The test limiters were exposed to H-mode deuterium plasmas with the neutral beam heating at maximum 5 MW for approximately 1 s. The power flux deposited on the test limiter was calculated by solving the 3-D heat conduction equation by using the measured time dependent surface temperatures as boundary conditions. The experimental results show that the heating with more radial NI beams leads to a higher local deposited power with a longer radial decay length related to banana particle loss. Strong localized W erosion was found at the tip of the test limiter due to arcing, which obviously depends on the neutral beam injection (NBI) geometry.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
M.Y. Ye, H. Maier, A. Herrmann, V. Rohde, H. Bolt, R. Neu, J. Neuhauser, ASDEX Upgrade Team ASDEX Upgrade Team,