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Title: Erosion characterization of SiC and Ti3SiC2 on DIII-D using focused ion beam micro-trenches

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.

Authors:
ORCiD logo; ORCiD logo; ; ; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
OSTI Identifier:
1529734
Alternate Identifier(s):
OSTI ID: 1528683
Grant/Contract Number:  
FC02-04ER54698; 5506; AC05-00OR22725
Resource Type:
Published Article
Journal Name:
Nuclear Materials and Energy
Additional Journal Information:
Journal Name: Nuclear Materials and Energy Journal Volume: 19 Journal Issue: C; Journal ID: ISSN 2352-1791
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 36 MATERIALS SCIENCE

Citation Formats

Coburn, J., Unterberg, E., Barton, J., Rudakov, D., Bykov, I., Parish, C. M., Wilcox, R., Lasnier, C., Abrams, T., Watkins, J., Hillis, D. L., and Bourham, M. Erosion characterization of SiC and Ti3SiC2 on DIII-D using focused ion beam micro-trenches. Netherlands: N. p., 2019. Web. doi:10.1016/j.nme.2019.02.036.
Coburn, J., Unterberg, E., Barton, J., Rudakov, D., Bykov, I., Parish, C. M., Wilcox, R., Lasnier, C., Abrams, T., Watkins, J., Hillis, D. L., & Bourham, M. Erosion characterization of SiC and Ti3SiC2 on DIII-D using focused ion beam micro-trenches. Netherlands. doi:10.1016/j.nme.2019.02.036.
Coburn, J., Unterberg, E., Barton, J., Rudakov, D., Bykov, I., Parish, C. M., Wilcox, R., Lasnier, C., Abrams, T., Watkins, J., Hillis, D. L., and Bourham, M. Wed . "Erosion characterization of SiC and Ti3SiC2 on DIII-D using focused ion beam micro-trenches". Netherlands. doi:10.1016/j.nme.2019.02.036.
@article{osti_1529734,
title = {Erosion characterization of SiC and Ti3SiC2 on DIII-D using focused ion beam micro-trenches},
author = {Coburn, J. and Unterberg, E. and Barton, J. and Rudakov, D. and Bykov, I. and Parish, C. M. and Wilcox, R. and Lasnier, C. and Abrams, T. and Watkins, J. and Hillis, D. L. and Bourham, M.},
abstractNote = {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.},
doi = {10.1016/j.nme.2019.02.036},
journal = {Nuclear Materials and Energy},
number = C,
volume = 19,
place = {Netherlands},
year = {2019},
month = {5}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
DOI: 10.1016/j.nme.2019.02.036

Citation Metrics:
Cited by: 1 work
Citation information provided by
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Figures / Tables:

Fig. 1 Fig. 1: (Left) DiMES head containing Ti3SiC2 and SiC samples, post-experiment. (Right) Schematic of typical angled DiMES sample, where each red cross represents a FIB micro-trench location. The general plasma flow follows the toroidal magnetic field Bt. (For interpretation of the references to color in this figure legend, the readermore » is referred to the web version of this article.)« less

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Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.