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.
| Original language | English |
|---|---|
| Pages (from-to) | 104-108 |
| Number of pages | 5 |
| Journal | Journal of Nuclear Materials |
| Volume | 337-339 |
| Issue number | 1-3 SPEC. ISS. |
| DOIs | |
| State | Published - 1 Mar 2005 |
| Externally published | Yes |
Keywords
- ASDEX Upgrade
- Erosion
- Poloidal limiter
- Power flux
- Tungsten coated carbon
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