Published October 1998 | Version v1
Journal article

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.