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.
| Originalsprache | Englisch |
|---|---|
| Seiten (von - bis) | 104-108 |
| Seitenumfang | 5 |
| Fachzeitschrift | Journal of Nuclear Materials |
| Jahrgang | 337-339 |
| Ausgabenummer | 1-3 SPEC. ISS. |
| DOIs | |
| Publikationsstatus | Veröffentlicht - 1 März 2005 |
| Extern publiziert | Ja |
Fingerprint
Untersuchen Sie die Forschungsthemen von „Tungsten limiter tests in ASDEX Upgrade“. Zusammen bilden sie einen einzigartigen Fingerprint.Dieses zitieren
- APA
- Author
- BIBTEX
- Harvard
- Standard
- RIS
- Vancouver