Erosion characterization of SiC and Ti                         3                         SiC                         2                          on DIII-D using focused ion beam micro-trenches

J. Coburn; E. Unterberg; J. Barton; D. Rudakov; I. Bykov; C. M. Parish; R. Wilcox; C. Lasnier; T. Abrams; J. Watkins; D. L. Hillis; M. Bourham

doi:10.1016/j.nme.2019.02.036

Erosion characterization of SiC and Ti ₃ SiC ₂ on DIII-D using focused ion beam micro-trenches

J. Coburn, E. Unterberg, J. Barton, D. Rudakov, I. Bykov, C. M. Parish, R. Wilcox, C. Lasnier, T. Abrams, J. Watkins, D. L. Hillis, M. Bourham

Research output: Contribution to journal › Article › peer-review

8 Scopus citations

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 ₃ SiC ₂ to both L- and H-mode plasma discharges in the DIII-D divertor. Samples survived average heat fluxes ranging from 2–10 MW/m ² over 16 s. A new micro-trench erosion measurement technique was successfully implemented and measured Ti ₃ SiC 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 B _t and ϕ = 51.5º–55º below the surface normal.

Original language	English
Pages (from-to)	316-323
Number of pages	8
Journal	Nuclear Materials and Energy
Volume	19
DOIs	https://doi.org/10.1016/j.nme.2019.02.036
State	Published - May 2019

Funding

This material is based upon work supported by the U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Awards DE-FC02-04ER54698. It is also supported by the DOE via UT Batelle, LLC Subcontract 4000145506. DIII-D data shown in this paper can be obtained in digital format by following the links at https://fusion.gat.com/global/D3D_DMP.CMP supported by an Early Career Award, US Department of Energy, Office of Science, Fusion Energy Sciences, under contract number DE-AC05-00OR22725. This work was performed in part at the Analytical Instrumentation Facility (AIF) at North Carolina State University, as well as the Low Activation Materials Development and Analysis (LAMDA) laboratory at Oak Ridge National Laboratory [28]. Disclaimer: This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. This material is based upon work supported by the U.S. Department of Energy , Office of Science , Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Awards DE-FC02-04ER54698 . It is also supported by the DOE via UT Batelle, LLC Subcontract 400014 5506 . DIII-D data shown in this paper can be obtained in digital format by following the links at https://fusion.gat.com/global/D3D_DMP . CMP supported by an Early Career Award, US Department of Energy , Office of Science , Fusion Energy Sciences , under contract number DE-AC05-00OR22725 . This work was performed in part at the Analytical Instrumentation Facility (AIF) at North Carolina State University, as well as the Low Activation Materials Development and Analysis (LAMDA) laboratory at Oak Ridge National Laboratory [28] . Disclaimer: This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

Funders	Funder number
DOE Office of Science user facility
US Department of Energy
U.S. Department of Energy	DE-FC02-04ER54698, 400014 5506
Office of Science	5506
Fusion Energy Sciences	DE-AC05-00OR22725

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Cite this

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. (2019). Erosion characterization of SiC and Ti ₃ SiC ₂ on DIII-D using focused ion beam micro-trenches Nuclear Materials and Energy, 19, 316-323. https://doi.org/10.1016/j.nme.2019.02.036

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title = " Erosion characterization of SiC and Ti 3 SiC 2 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 3 SiC 2 to both L- and H-mode plasma discharges in the DIII-D divertor. Samples survived average heat fluxes ranging from 2–10 MW/m 2 over 16 s. A new micro-trench erosion measurement technique was successfully implemented and measured Ti 3 SiC 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 B t and ϕ = 51.5º–55º below the surface normal.",

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Coburn, J, Unterberg, E, Barton, J, Rudakov, D, Bykov, I, Parish, CM , Wilcox, R, Lasnier, C, Abrams, T, Watkins, J, Hillis, DL & Bourham, M 2019, ' Erosion characterization of SiC and Ti ₃ SiC ₂ on DIII-D using focused ion beam micro-trenches ', Nuclear Materials and Energy, vol. 19, pp. 316-323. https://doi.org/10.1016/j.nme.2019.02.036

Erosion characterization of SiC and Ti ₃ SiC ₂ on DIII-D using focused ion beam micro-trenches . / Coburn, J.; Unterberg, E.; Barton, J. et al.
In: Nuclear Materials and Energy, Vol. 19, 05.2019, p. 316-323.

Research output: Contribution to journal › Article › peer-review

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AU - Bykov, I.

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AU - Wilcox, R.

AU - Lasnier, C.

AU - Abrams, T.

AU - Watkins, J.

AU - Hillis, D. L.

AU - Bourham, M.

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Coburn J, Unterberg E, Barton J, Rudakov D, Bykov I, Parish CM et al. Erosion characterization of SiC and Ti ₃ SiC ₂ on DIII-D using focused ion beam micro-trenches Nuclear Materials and Energy. 2019 May;19:316-323. doi: 10.1016/j.nme.2019.02.036