Evaluation of silicon carbide as a divertor armor material in DIII-D H-mode discharges
Abstract
Silicon carbide (SiC) represents a promising but largely untested plasma-facing material (PFM) for next-step fusion devices. In this work, an analytic mixed-material erosion model is developed by calculating the physical (via SDTrimSP) and chemical (via empirical scalings) sputtering yield from SiC, Si, and C. The Si content in the near-surface SiC layer is predicted to increase during D plasma bombardment due to more efficient physical and chemical sputtering of C relative to Si. Silicon erosion from SiC thereby occurs primarily from sputtering of the enriched Si layer, rather than directly from the SiC itself. SiC coatings on ATJ graphite, manufactured via chemical vapor deposition, were exposed to repeated H-mode plasma discharges in the DIII-D tokamak to test this model. The qualitative trends from analytic modeling are reproduced by the experimental measurements, obtained via spectroscopic inference using the S/XB method. Quantitatively the model slightly under-predicts measured erosion rates, which is attributed to uncertainties in the ion impact angle distribution, as well as the effect of edge-localized modes. After exposure, minimal changes to the macroscopic or microscopic surface morphology of the SiC coatings were observed. Compositional analysis reveals Si enrichment of about 10%, in line with expectations from the erosion model. Extrapolatingmore »
- Authors:
-
- General Atomics, San Diego, CA (United States)
- Univ. of California San Diego, La Jolla, CA (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Publication Date:
- Research Org.:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); General Atomics, San Diego, CA (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities Division
- OSTI Identifier:
- 1874541
- Alternate Identifier(s):
- OSTI ID: 1784024; OSTI ID: 1818709
- Report Number(s):
- LLNL-JRNL-836399
Journal ID: ISSN 0029-5515; 1055687; TRN: US2307125
- Grant/Contract Number:
- AC52-07NA27344; FC02-04ER54698; AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Fusion
- Additional Journal Information:
- Journal Volume: 61; Journal Issue: 6; Journal ID: ISSN 0029-5515
- Publisher:
- IOP Science
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; DIII-D; silicon carbide; SiC; sputtering; erosion; plasma-materials interactions; divertor
Citation Formats
Abrams, Tyler, Bringuier, Stefan A., Thomas, Dan M., Sinclair, Gregory, Gonderman, S., Holland, L., Rudakov, Dmitry L., Wilcox, Robert S., Unterberg, Ezekial A., and Scotti, Filippo. Evaluation of silicon carbide as a divertor armor material in DIII-D H-mode discharges. United States: N. p., 2021.
Web. doi:10.1088/1741-4326/abecee.
Abrams, Tyler, Bringuier, Stefan A., Thomas, Dan M., Sinclair, Gregory, Gonderman, S., Holland, L., Rudakov, Dmitry L., Wilcox, Robert S., Unterberg, Ezekial A., & Scotti, Filippo. Evaluation of silicon carbide as a divertor armor material in DIII-D H-mode discharges. United States. https://doi.org/10.1088/1741-4326/abecee
Abrams, Tyler, Bringuier, Stefan A., Thomas, Dan M., Sinclair, Gregory, Gonderman, S., Holland, L., Rudakov, Dmitry L., Wilcox, Robert S., Unterberg, Ezekial A., and Scotti, Filippo. Wed .
"Evaluation of silicon carbide as a divertor armor material in DIII-D H-mode discharges". United States. https://doi.org/10.1088/1741-4326/abecee. https://www.osti.gov/servlets/purl/1874541.
@article{osti_1874541,
title = {Evaluation of silicon carbide as a divertor armor material in DIII-D H-mode discharges},
author = {Abrams, Tyler and Bringuier, Stefan A. and Thomas, Dan M. and Sinclair, Gregory and Gonderman, S. and Holland, L. and Rudakov, Dmitry L. and Wilcox, Robert S. and Unterberg, Ezekial A. and Scotti, Filippo},
abstractNote = {Silicon carbide (SiC) represents a promising but largely untested plasma-facing material (PFM) for next-step fusion devices. In this work, an analytic mixed-material erosion model is developed by calculating the physical (via SDTrimSP) and chemical (via empirical scalings) sputtering yield from SiC, Si, and C. The Si content in the near-surface SiC layer is predicted to increase during D plasma bombardment due to more efficient physical and chemical sputtering of C relative to Si. Silicon erosion from SiC thereby occurs primarily from sputtering of the enriched Si layer, rather than directly from the SiC itself. SiC coatings on ATJ graphite, manufactured via chemical vapor deposition, were exposed to repeated H-mode plasma discharges in the DIII-D tokamak to test this model. The qualitative trends from analytic modeling are reproduced by the experimental measurements, obtained via spectroscopic inference using the S/XB method. Quantitatively the model slightly under-predicts measured erosion rates, which is attributed to uncertainties in the ion impact angle distribution, as well as the effect of edge-localized modes. After exposure, minimal changes to the macroscopic or microscopic surface morphology of the SiC coatings were observed. Compositional analysis reveals Si enrichment of about 10%, in line with expectations from the erosion model. Extrapolating to a DEMO-type device, an order-of-magnitude decrease in impurity sourcing, and up to a factor of 2 decrease in impurity radiation, is expected with SiC walls, relative to graphite, if low C plasma impurity content can be achieved. Furthermore, these favorable erosion properties motivate further investigations of SiC as a low-Z, non-metallic PFM.},
doi = {10.1088/1741-4326/abecee},
journal = {Nuclear Fusion},
number = 6,
volume = 61,
place = {United States},
year = {Wed Apr 21 00:00:00 EDT 2021},
month = {Wed Apr 21 00:00:00 EDT 2021}
}
Works referenced in this record:
Overview of the results on divertor heat loads in RMP controlled H-mode plasmas on DIII-D
journal, August 2009
- Jakubowski, M. W.; Evans, T. E.; Fenstermacher, M. E.
- Nuclear Fusion, Vol. 49, Issue 9
Initial operation of the divertor Thomson scattering diagnostic on DIII-D
journal, February 1997
- Carlstrom, T. N.; Hsieh, C. L.; Stockdale, R.
- Review of Scientific Instruments, Vol. 68, Issue 2
DIII-D research towards establishing the scientific basis for future fusion reactors
journal, June 2019
- Petty, C. C.
- Nuclear Fusion, Vol. 59, Issue 11
Redeposition of SiC-coated graphite limiter in Alcator C
journal, May 1987
- Megusar, J.; Yang, T. F.; Martin, J. R.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 23, Issue 4
Handbook of SiC properties for fuel performance modeling
journal, September 2007
- Snead, Lance L.; Nozawa, Takashi; Katoh, Yutai
- Journal of Nuclear Materials, Vol. 371, Issue 1-3
Impact of ELM control techniques on tungsten sputtering in the DIII-D divertor and extrapolations to ITER
journal, June 2019
- Abrams, T.; Unterberg, E. A.; Rudakov, D. L.
- Physics of Plasmas, Vol. 26, Issue 6
Impact of gyro-motion and sheath acceleration on the flux distribution on rough surfaces
journal, August 2010
- Schmid, K.; Mayer, M.; Adelhelm, C.
- Nuclear Fusion, Vol. 50, Issue 10
Chapter 10: Plasma-Wall Interaction and First-Wall Materials in ASDEX Upgrade
journal, November 2003
- Neu, Rudolf; Kallenbach, Arne; Krieger, Karl
- Fusion Science and Technology, Vol. 44, Issue 3
Observations of wall conditioning by means of boron powder injection in DIII-D H-mode plasmas
journal, September 2020
- Bortolon, A.; Maingi, R.; Nagy, A.
- Nuclear Fusion, Vol. 60, Issue 12
Control of high-Z PFC erosion by local gas injection in DIII-D
journal, August 2015
- Rudakov, D. L.; Stangeby, P. C.; Wong, C. P. C.
- Journal of Nuclear Materials, Vol. 463
Plasma-wall interactions in ITER
journal, February 1997
- Parker, R.; Janeschitz, G.; Pacher, H. D.
- Journal of Nuclear Materials, Vol. 241-243
Radiation stable, hybrid, chemical vapor infiltration/preceramic polymer joining of silicon carbide components
journal, April 2017
- Khalifa, Hesham E.; Koyanagi, Takaaki; Jacobsen, George M.
- Journal of Nuclear Materials, Vol. 487
Physics basis for the first ITER tungsten divertor
journal, August 2019
- Pitts, R. A.; Bonnin, X.; Escourbiac, F.
- Nuclear Materials and Energy, Vol. 20
Implications of PMI and wall material choice on fusion reactor tritium self-sufficiency
journal, January 2019
- Doerner, R. P.; Tynan, G. R.; Schmid, K.
- Nuclear Materials and Energy, Vol. 18
A tangentially viewing vacuum ultraviolet TV system for the DIII–D divertor
journal, January 1999
- Nilson, D. G.; Fenstermacher, M. E.; Ellis, R.
- Review of Scientific Instruments, Vol. 70, Issue 1
Molybdenum, Carbon and Silicon Carbide Limiter Experiment in the JFT-2 Tokamak
journal, July 1979
- Gomay, Yoshio; Konoshima, Shigeru; Fujisawa, Noboru
- Japanese Journal of Applied Physics, Vol. 18, Issue 7
Calculation of D/XB Values of Hydrocarbon Molecules in Tokamak Edge Plasmas
journal, January 2010
- Kawazome, Hayato; Ohya, Kaoru; Inai, Kensuke
- Plasma and Fusion Research, Vol. 5
Sputtering of limiter and divertor materials
journal, December 1990
- Roth, J.
- Journal of Nuclear Materials, Vol. 176-177
Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects
journal, May 2014
- Katoh, Yutai; Ozawa, Kazumi; Shih, Chunghao
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Deuterium retention in silicon carbide, SiC ceramic matrix composites, and SiC coated graphite
journal, August 2019
- Koller, Markus T.; Davis, James W.; Goodland, Megan E.
- Nuclear Materials and Energy, Vol. 20
ADAS: Atomic data, modelling and analysis for fusion
conference, January 2007
- Summers, H. P.; O’Mullane, M. G.; Whiteford, A. D.
- ATOMIC AND MOLECULAR DATA AND THEIR APPLICATIONS: 5th International Conference on Atomic and Molecular Data and Their Applications (ICAMDATA), AIP Conference Proceedings
Wall conditioning in fusion devices and its influence on plasma performance
journal, September 1996
- Winter, J.
- Plasma Physics and Controlled Fusion, Vol. 38, Issue 9
Long pulse enhanced confinement discharges in the HT-7 superconducting tokamak by ion Bernstein wave heating and lower hybrid wave current drive
journal, May 2003
- Li, J.; Wan, B. N.; Luo, J. R.
- Physics of Plasmas, Vol. 10, Issue 5
Net versus gross erosion of silicon carbide in DIII-D divertor
journal, January 2020
- Rudakov, D. L.; Wampler, W. R.; Abrams, T.
- Physica Scripta, Vol. T171
Determination of rate coefficients for fusion-relevant atoms and molecules by modelling and measurement in the boundary layer of TEXTOR
journal, July 2010
- Pospieszczyk, A.; Borodin, D.; Brezinsek, S.
- Journal of Physics B: Atomic, Molecular and Optical Physics, Vol. 43, Issue 14
Sputtering and codeposition of silicon carbide with deuterium
journal, March 2003
- Causey, Rion A.
- Journal of Nuclear Materials, Vol. 313-316
Advances in understanding of high- Z material erosion and re-deposition in low- Z wall environment in DIII-D
journal, March 2017
- Ding, R.; Rudakov, D. L.; Stangeby, P. C.
- Nuclear Fusion, Vol. 57, Issue 5
Material erosion at the vessel walls of future fusion devices
journal, March 2003
- Behrisch, R.; Federici, G.; Kukushkin, A.
- Journal of Nuclear Materials, Vol. 313-316
Characterization of SiC–SiC composites for accident tolerant fuel cladding
journal, November 2015
- Deck, C. P.; Jacobsen, G. M.; Sheeder, J.
- Journal of Nuclear Materials, Vol. 466
Experimental verification of ion impact angle distribution at divertor surfaces using micro-engineered targets on DiMES at DIII-D
journal, June 2021
- Abe, S.; Skinner, C. H.; Bykov, I.
- Nuclear Materials and Energy, Vol. 27
Erosion behaviour and surface composition modifications of SiC under D+ ion bombardment
journal, April 1996
- Plank, H.; Schwörer, R.; Roth, J.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 111, Issue 1-2
Type-I ELM power deposition profile width and temporal shape in JET
journal, August 2011
- Eich, T.; Thomsen, H.; Fundamenski, W.
- Journal of Nuclear Materials, Vol. 415, Issue 1
Chemical erosion of different carbon composites under ITER-relevant plasma conditions
journal, December 2009
- Westerhout, J.; Borodin, D.; Al, R. S.
- Physica Scripta, Vol. T138
The inter-ELM tungsten erosion profile in DIII-D H-mode discharges and benchmarking with ERO+OEDGE modeling
journal, April 2017
- Abrams, T.; Ding, R.; Guo, H. Y.
- Nuclear Fusion, Vol. 57, Issue 5
Characterization of the helicon plasma flux to the target of Proto-MPEX
journal, January 2019
- Beers, C. J.; Lindquist, E. G.; Biewer, T. M.
- Fusion Engineering and Design, Vol. 138
Comparison of the chemical erosion of Si, C and SiC under deuterium ion bombardment
journal, June 2000
- Balden, M.; Roth, J.
- Journal of Nuclear Materials, Vol. 279, Issue 2-3
Plasma edge physics with siliconization in TEXTOR
journal, April 1995
- Samm, U.; Bogen, P.; Esser, G.
- Journal of Nuclear Materials, Vol. 220-222
Nitrile, Latex, Neoprene and Vinyl Gloves: A Primary Source of Contamination for Trace Element and Zn Isotopic Analyses in Geological and Biological Samples
journal, January 2017
- Garçon, Marion; Sauzéat, Lucie; Carlson, Richard W.
- Geostandards and Geoanalytical Research, Vol. 41, Issue 3
Quantifying erosion and retention of silicon carbide due to D plasma irradiation in a high-flux linear plasma device
journal, March 2021
- Sinclair, G.; Abrams, T.; Bringuier, S.
- Nuclear Materials and Energy, Vol. 26
Determination of photon efficiencies and hydrocarbon influxes in the detached outer divertor plasma of ASDEX Upgrade
journal, March 2007
- Brezinsek, S.; Pugno, R.; Fantz, U.
- Physica Scripta, Vol. T128
Quantification of chemical erosion in the DIII-D divertor and implications for ITER
journal, August 2011
- McLean, A. G.; Stangeby, P. C.; Bray, B. D.
- Journal of Nuclear Materials, Vol. 415, Issue 1
Chemical erosion of carbon based materials in fusion devices
journal, March 1999
- Roth, Joachim
- Journal of Nuclear Materials, Vol. 266-269
Multichord spectroscopy of the DIII‐D divertor region
journal, October 1992
- Brooks, N. H.; Howald, A.; Klepper, K.
- Review of Scientific Instruments, Vol. 63, Issue 10
Fabrication of SiC–SiC composites for fuel cladding in advanced reactor designs
journal, May 2012
- Deck, C. P.; Khalifa, H. E.; Sammuli, B.
- Progress in Nuclear Energy, Vol. 57
Atomic insight into concurrent He, D, and T sputtering and near-surface implantation of 3C-SiC crystallographic surfaces
journal, May 2019
- Bringuier, S.; Abrams, T.; Guterl, J.
- Nuclear Materials and Energy, Vol. 19
Mechanism of the chemical erosion of SiC under hydrogen irradiation
journal, March 2001
- Balden, M.; Picarle, S.; Roth, J.
- Journal of Nuclear Materials, Vol. 290-293
Experimental validation of an analytical kinetic model for edge-localized modes in JET-ITER-like wall
journal, April 2018
- Guillemaut, C.; Metzger, C.; Moulton, D.
- Nuclear Fusion, Vol. 58, Issue 6
Tungsten erosion by unipolar arcing in DIII-D
journal, October 2017
- Bykov, I.; Chrobak, C. P.; Abrams, T.
- Physica Scripta, Vol. T170
Zinc accelerator complexes.
journal, February 2001
- Nieuwenhuizen, Peter J.
- Applied Catalysis A: General, Vol. 207, Issue 1-2
The ARIES-AT advanced tokamak, Advanced technology fusion power plant
journal, January 2006
- Najmabadi, Farrokh; Abdou, A.; Bromberg, L.
- Fusion Engineering and Design, Vol. 80, Issue 1-4
Hydrocarbon injection for quantification of chemical erosion yields in tokamaks
journal, June 2007
- Brezinsek, S.; Pospieszczyk, A.; Borodin, D.
- Journal of Nuclear Materials, Vol. 363-365