High heat flux erosion of carbon fibre composite materials in the TEXTOR tokamak.
During plasma disruptions, ELMs, or vertical displacement events (VDEs) high transient heat loads to the plasma facing materials an cause damage such as thermal erosion, cracking, or melting. Self shielding processes, which take place when a material surface is exposed to a high heat flux from an incident plasma, can lead to a reduction of the deposited energy. Experiments using the fast pneumatic probe of the TEXTOR tokamak were carried out to investigate these effects. The materials tested were carbon fibre reinforced materials with and without Si-addition. The probe with the material specimens was introduced into the edge plasma up to a depth of 9 cm in front of the ALT41 main limiter with a residence time of 80 ms. After the repeated exposure to the TEXTOR-plasma, the material specimens were examined by profilometry and electron microscopy to determine the damage and erosion. It was found that only a very limited zone of the probe tip of about 2.5 mm extension in radial direction showed erosion. The maximum erosion was observed at the very tip of the probe with approx. 30 {micro}m per exposure. The results of the erosion quantification are compared with the results from numerical simulations and from plasma diagnostic measurements during the exposure of the specimens.
- Research Organization:
- Argonne National Lab., IL (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10679
- Report Number(s):
- ANL/TD/CP-95856; TRN: AH200127%%387
- Resource Relation:
- Conference: 8th International Conference on Fusion Reactor Materials (ICFRM-8), Sendai (JP), 10/26/1997--10/31/1997; Other Information: PBD: 10 Mar 1998
- Country of Publication:
- United States
- Language:
- English
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