skip to main content
DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

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 Ti 3SiC 2 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 Ti 3SiC 2 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 [1]; ORCiD logo [2];  [3];  [4];  [4]; ORCiD logo [2]; ORCiD logo [2];  [5];  [1];  [3]; ORCiD logo [2];  [6]
  1. General Atomics, San Diego, CA (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Sandia National Lab. (SNL-CA), Livermore, CA (United States); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  4. Univ. of California, San Diego, CA (United States)
  5. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  6. North Carolina State Univ., Raleigh, NC (United States)
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) (SC-24)
OSTI Identifier:
1529734
Alternate Identifier(s):
OSTI ID: 1528683
Grant/Contract Number:  
AC05-00OR22725; FC02-04ER54698; 5506
Resource Type:
Published Article
Journal Name:
Nuclear Materials and Energy
Additional Journal Information:
Journal Volume: 19; Journal Issue: C; Journal ID: ISSN 2352-1791
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 36 MATERIALS SCIENCE

Citation Formats

Coburn, Jonathan, Unterberg, Ezekial, Barton, J, Rudakov, D.L., Bykov, Igor, Parish, Chad M., Wilcox, Robert, Lasnier, C.J., Abrams, Tyler, Watkins, J. G., Hillis, Donald Lee, and Bourham, Mohamed. Erosion characterization of SiC and Ti3SiC2 on DIII-D using focused ion beam micro-trenches. United States: N. p., 2019. Web. doi:10.1016/j.nme.2019.02.036.
Coburn, Jonathan, Unterberg, Ezekial, Barton, J, Rudakov, D.L., Bykov, Igor, Parish, Chad M., Wilcox, Robert, Lasnier, C.J., Abrams, Tyler, Watkins, J. G., Hillis, Donald Lee, & Bourham, Mohamed. Erosion characterization of SiC and Ti3SiC2 on DIII-D using focused ion beam micro-trenches. United States. doi:10.1016/j.nme.2019.02.036.
Coburn, Jonathan, Unterberg, Ezekial, Barton, J, Rudakov, D.L., Bykov, Igor, Parish, Chad M., Wilcox, Robert, Lasnier, C.J., Abrams, Tyler, Watkins, J. G., Hillis, Donald Lee, and Bourham, Mohamed. Thu . "Erosion characterization of SiC and Ti3SiC2 on DIII-D using focused ion beam micro-trenches". United States. 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, Jonathan and Unterberg, Ezekial and Barton, J and Rudakov, D.L. and Bykov, Igor and Parish, Chad M. and Wilcox, Robert and Lasnier, C.J. and Abrams, Tyler and Watkins, J. G. and Hillis, Donald Lee and Bourham, Mohamed},
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 = {United States},
year = {2019},
month = {3}
}

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

Save / Share: