High heat flux erosion of carbon fibre composite materials in the TEXTOR tokamak
- 1. Forschungszentrum Juelich GmbH (Germany). Inst. fuer Werkstoffe der Energietechnik
- 2. California Univ., San Diego, CA (United States). Fusion Energy Program
- 3. Argonne National Lab., IL (United States). Fusion Power Program
Description
During plasma disruptions, ELMs, or vertical displacement events (VDEs) high transient heat loads to the plasma facing materials can 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 ALT-II 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 μm 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. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 258-263
- Journal Issue
- pt.A
- Journal Page Range
- p. 757-763
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- 8. international conference on fusion reactor materials (ICFRM-8)
- Dates
- 26-31 Oct 1997
- Place
- Sendai (Japan)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 30005510
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; DIVERTORS; EROSION; HEAT FLUX; LIMITERS; MELTING; PLASMA DENSITY; PLASMA DISRUPTION; TEXTOR TOKAMAK; THERMONUCLEAR REACTOR WALLS; TRANSMISSION ELECTRON MICROSCOPY; WEAR
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRON MICROSCOPY; MICROSCOPY; PHASE TRANSFORMATIONS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Notes
- 13 refs.