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Erosion characterization of SiC and Ti3SiC2 on DIII-D using focused ion beam micro-trenches
- Source :
- Nuclear Materials and Energy, Vol 19, Iss, Pp 316-323 (2019)
- Publication Year :
- 2019
- Publisher :
- Elsevier BV, 2019.
-
Abstract
- Plasma-facing materials in future large-scale fusion reactors must be designed to withstand high heat fluxes from extreme off-normal events such as edge localized modes and unmitigated plasma disruptions. The erosion rates of possible tungsten-alternative materials are tested under high heat flux conditions at the DIII-D National Fusion Facility. High-purity β-3C CVD silicon carbide was exposed alongside MAX phase ceramic Ti3SiC2 to both L- and H-mode plasma discharges in the DIII-D divertor. Samples survived average heat fluxes ranging from 2–10 MW/m2 over 16 s. A new micro-trench erosion measurement technique was successfully implemented and measured Ti3SiC2 and SiC erosion rates of 0–9 nm/s and 27–73 nm/s, respectively. Additionally, average ion impact angle estimates for an incident B-field angle of ∼1.5° from surface parallel were made using micro-trench impact patterns. Measurements ranged from θ = 24o–34o with respect to Bt and ϕ = 51.5o–55o below the surface normal.
- Subjects :
- 010302 applied physics
Nuclear and High Energy Physics
Materials science
DIII-D
Materials Science (miscellaneous)
Divertor
Nuclear engineering
Plasma
Fusion power
lcsh:TK9001-9401
01 natural sciences
Focused ion beam
010305 fluids & plasmas
chemistry.chemical_compound
Nuclear Energy and Engineering
chemistry
visual_art
0103 physical sciences
Erosion
visual_art.visual_art_medium
Silicon carbide
lcsh:Nuclear engineering. Atomic power
Ceramic
Subjects
Details
- ISSN :
- 23521791
- Volume :
- 19
- Database :
- OpenAIRE
- Journal :
- Nuclear Materials and Energy
- Accession number :
- edsair.doi.dedup.....a14371d036373d50e516e8636100b595
- Full Text :
- https://doi.org/10.1016/j.nme.2019.02.036