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Demonstration of suppression of dust generation and partial reduction of the hydrogen retention by tungsten coated graphite divertor tiles in LHD
- Source :
- Nuclear Materials and Energy, Vol 18, Iss, Pp 23-28 (2019)
- Publication Year :
- 2019
- Publisher :
- Elsevier, 2019.
-
Abstract
- Three sets of tungsten coated graphite divertor tiles (VPS-W tiles) were installed in the closed helical divertor of the Large Helical Device (LHD) instead of the graphite divertor tiles in the 2012FY plasma campaign for examining the plasma wall interaction (PWI) with divertor plasma. The first wall panels and divertor tiles of the LHD consist of stainless steels (SUS316L) and graphite, respectively. The carbon based mixed-material deposition layer including a very small amount of Fe element has been formed on not only the divertor tiles but also the first walls near the divertor tiles through the PWI processes. Such a mixed layer often causes undesirable influences for maintaining a long pulse discharge in LHD, e.g., changing the particle recycling properties and dust generation. After the single plasma campaign of the 2012FY, we confirmed drastic suppression of the mixed-material deposition layer on the first wall panels just under the VPS-W tiles. On the other hand, carbon based mixed-material deposition layer was formed on the VPS-W tile surface, where the amount of the hydrogen retention was estimated to be over ∼4 × 1021 H/m2. If we would want further suppression of the hydrogen retention on the VPS-W tiles, the plasma facing components should be replaced to a full metal wall to avoid formation of the carbon co-deposition layer. Keywords: Tungsten divertor, Dust, Hydrogen retention
- Subjects :
- 010302 applied physics
Nuclear and High Energy Physics
Materials science
Materials Science (miscellaneous)
Divertor
chemistry.chemical_element
Plasma
Tungsten
01 natural sciences
lcsh:TK9001-9401
010305 fluids & plasmas
Large Helical Device
Nuclear Energy and Engineering
chemistry
visual_art
0103 physical sciences
visual_art.visual_art_medium
lcsh:Nuclear engineering. Atomic power
Graphite
Tile
Composite material
Layer (electronics)
Carbon
Subjects
Details
- Language :
- English
- ISSN :
- 23521791
- Volume :
- 18
- Database :
- OpenAIRE
- Journal :
- Nuclear Materials and Energy
- Accession number :
- edsair.doi.dedup.....f8c920be6f1bcedfba4a2cdb8ca03b64