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Temperature impact on W surface exposed to He plasma in LHD and its consequences for the material properties
- Source :
- Journal of Nuclear Materials. 463:316-319
- Publication Year :
- 2015
- Publisher :
- Elsevier BV, 2015.
-
Abstract
- A new temperature controlled material probe was designed for the exposure of W samples to He plasma in the LHD (Large Helical Device). TEM (Transmission Electron Microscopy) analysis allowed the study of the impact of He irradiation under high temperatures (up to 600 °C) on W microstructure: bubbles and dislocation loops are formed at the surface. A heavily damaged layer rich in both damages is formed at the very surface layer whose thickness increases with the incident fluence; beyond this layer, bubbles are observed much deeper than expected, rising concerns about the consequences for the material properties conservation. Nano-indentation measurements showed that the hardness of exposed tungsten indeed increases as the dislocation loops are formed and large bubbles appear in the material.
- Subjects :
- Nuclear and High Energy Physics
Materials science
chemistry.chemical_element
Tungsten
Microstructure
Fluence
Large Helical Device
Crystallography
Nuclear Energy and Engineering
chemistry
Transmission electron microscopy
General Materials Science
Surface layer
Irradiation
Dislocation
Composite material
Subjects
Details
- ISSN :
- 00223115
- Volume :
- 463
- Database :
- OpenAIRE
- Journal :
- Journal of Nuclear Materials
- Accession number :
- edsair.doi...........1dc233a24c9e0e4b3c85b64f1b54d742