Net versus gross erosion of silicon carbide in DIII-D divertor

Rudakov, D. L.; Wampler, W. R.; Abrams, T.; Ding, R.; Boedo, J. A.; Bringuier, S.; Bykov, I.; Chrobak, C. P.; Elder, J. D.; Guo, H. Y.; Lasnier, C. J.; Mathison, E.; McLean, A. G.; Sinclair, G.; Stangeby, P. C.; Thomas, D. M.; Unterberg, E. A.; Wang, H.; Watkins, J. G.

doi:10.1088/1402-4896/ab61dc

Title: Net versus gross erosion of silicon carbide in DIII-D divertor

Abstract

Gross and net erosion rates of silicon from silicon carbide (SiC) coatings were measured in the divertor of DIII-D under well diagnosed reactor-relevant plasma conditions. Amorphous and crystalline SiC coatings on graphite with thickness of ~80 nm and ~250 μm, respectively, were exposed near an attached outer strike point of lower single null L-mode plasmas using the Divertor Material Evaluation System (DiMES). Plasma density and electron temperature near the center of the coatings were n_e ~ 4 × 10¹⁹ m^-3 and T _e ~ 23 eV. Gross erosion of Si from all samples was measured spectroscopically using the Si II 636 nm line. It was found to be a factor of ~4 higher for the amorphous coatings compared to the crystalline one. The thin amorphous coatings allowed measurements of net Si erosion with Rutherford backscattering. Net average Si erosion rate of ~3 × 10¹⁶ cm^-2 s^-1 was measured on the amorphous coatings with toroidal extent of 1 mm, where, according to ERO code modeling, the local redeposition of Si was about 30%. Using this rate, spectroscopic measurements, measured D⁺ ion fluxes, and corrections from ERO-OEDGE modeling, effective SXB coefficient for the Si II 636 nm line of ~52 and Simore »« less

Authors:

^[1];

^[2];

^[3]; Ding, R. ^[4]; Boedo, J. A. ^[1];

^[3];

^[1];

^[3]; Elder, J. D. ^[5]; Guo, H. Y. ^[3]; Lasnier, C. J. ^[6]; Mathison, E. ^[3]; McLean, A. G. ^[6];

^[7];

^[5]; Thomas, D. M. ^[3];

^[7]; Wang, H. ^[3]; Watkins, J. G. ^[8]

Univ. of California, San Diego, CA (United States)
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
General Atomics, San Diego, CA (United States)
Chinese Academy of Sciences (CAS), Hefei (China)
Univ. of Toronto, ON (Canada)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sandia National Lab. (SNL-CA), Livermore, CA (United States)

Publication Date:: Wed Mar 18 00:00:00 EDT 2020

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Sponsoring Org.:: USDOE National Nuclear Security Administration (NNSA); National Natural Science Foundation of China (NSFC)

OSTI Identifier:: 1832712

Alternate Identifier(s):: OSTI ID: 1860688

Report Number(s):: LLNL-JRNL-830756
Journal ID: ISSN 0031-8949; TRN: US2216761

Grant/Contract Number:: AC05-00OR22725; FG02-07ER54917; FC02-04ER54698; NA0003525; AC52-07NA27344; SC0018423; 11861131010; 11675218

Resource Type:: Accepted Manuscript

Journal Name:: Physica Scripta

Additional Journal Information:: Journal Volume: T171; Journal Issue: T171; Journal ID: ISSN 0031-8949

Publisher:: IOP Publishing

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; DIII-D tokamak; DiMES; silicon carbide

Citation Formats


                    Rudakov, D. L., Wampler, W. R., Abrams, T., Ding, R., Boedo, J. A., Bringuier, S., Bykov, I., Chrobak, C. P., Elder, J. D., Guo, H. Y., Lasnier, C. J., Mathison, E., McLean, A. G., Sinclair, G., Stangeby, P. C., Thomas, D. M., Unterberg, E. A., Wang, H., and Watkins, J. G. Net versus gross erosion of silicon carbide in DIII-D divertor.  United States: N. p., 2020. 
Web.  doi:10.1088/1402-4896/ab61dc.

Copy to clipboard


                    Rudakov, D. L., Wampler, W. R., Abrams, T., Ding, R., Boedo, J. A., Bringuier, S., Bykov, I., Chrobak, C. P., Elder, J. D., Guo, H. Y., Lasnier, C. J., Mathison, E., McLean, A. G., Sinclair, G., Stangeby, P. C., Thomas, D. M., Unterberg, E. A., Wang, H., & Watkins, J. G. Net versus gross erosion of silicon carbide in DIII-D divertor.  United States.  https://doi.org/10.1088/1402-4896/ab61dc

Copy to clipboard


                    Rudakov, D. L., Wampler, W. R., Abrams, T., Ding, R., Boedo, J. A., Bringuier, S., Bykov, I., Chrobak, C. P., Elder, J. D., Guo, H. Y., Lasnier, C. J., Mathison, E., McLean, A. G., Sinclair, G., Stangeby, P. C., Thomas, D. M., Unterberg, E. A., Wang, H., and Watkins, J. G. Wed .  
"Net versus gross erosion of silicon carbide in DIII-D divertor".  United States.  https://doi.org/10.1088/1402-4896/ab61dc.  https://www.osti.gov/servlets/purl/1832712.

Copy to clipboard


                    
@article{osti_1832712,

  title        = {Net versus gross erosion of silicon carbide in DIII-D divertor},

  author       = {Rudakov, D. L. and Wampler, W. R. and Abrams, T. and Ding, R. and Boedo, J. A. and Bringuier, S. and Bykov, I. and Chrobak, C. P. and Elder, J. D. and Guo, H. Y. and Lasnier, C. J. and Mathison, E. and McLean, A. G. and Sinclair, G. and Stangeby, P. C. and Thomas, D. M. and Unterberg, E. A. and Wang, H. and Watkins, J. G.},

  abstractNote = {Gross and net erosion rates of silicon from silicon carbide (SiC) coatings were measured in the divertor of DIII-D under well diagnosed reactor-relevant plasma conditions. Amorphous and crystalline SiC coatings on graphite with thickness of ~80 nm and ~250 μm, respectively, were exposed near an attached outer strike point of lower single null L-mode plasmas using the Divertor Material Evaluation System (DiMES). Plasma density and electron temperature near the center of the coatings were ne ~ 4 × 1019 m-3 and T e ~ 23 eV. Gross erosion of Si from all samples was measured spectroscopically using the Si II 636 nm line. It was found to be a factor of ~4 higher for the amorphous coatings compared to the crystalline one. The thin amorphous coatings allowed measurements of net Si erosion with Rutherford backscattering. Net average Si erosion rate of ~3 × 1016 cm-2 s-1 was measured on the amorphous coatings with toroidal extent of 1 mm, where, according to ERO code modeling, the local redeposition of Si was about 30%. Using this rate, spectroscopic measurements, measured D+ ion fluxes, and corrections from ERO-OEDGE modeling, effective SXB coefficient for the Si II 636 nm line of ~52 and Si sputtering yield of ~0.017 Si/D were calculated. Finally, deuterium retention on SiC coatings was measured by 2.5 MeV 3He nuclear reaction analysis at 0.5–2.5 × 1017 atoms cm-2, consistent with retention due to implantation into a surface undergoing net erosion.},

  doi          = {10.1088/1402-4896/ab61dc},

  journal      = {Physica Scripta},

  number       = T171,

  volume       = T171,

  place        = {United States},

  year         = {Wed Mar 18 00:00:00 EDT 2020},

  month        = {Wed Mar 18 00:00:00 EDT 2020}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1088/1402-4896/ab61dc

Other availability

Search WorldCat to find libraries that may hold this journal

Save / Share:

Export Metadata

Save to My Library

Works referenced in this record:

A design retrospective of the DIII-D tokamak
journal, May 2002

Luxon, J. L.
Nuclear Fusion, Vol. 42, Issue 5
DOI: 10.1088/0029-5515/42/5/313

Divertor materials evaluation system (DiMES)
journal, October 1998

Wong, C. P. C.; Whyte, D. G.; Bastasz, R. J.
Journal of Nuclear Materials, Vol. 258-263
DOI: 10.1016/S0022-3115(98)00407-3

An experimental comparison of gross and net erosion of Mo in the DIII-D divertor
journal, July 2013

Stangeby, P. C.; Rudakov, D. L.; Wampler, W. R.
Journal of Nuclear Materials, Vol. 438
DOI: 10.1016/j.jnucmat.2013.01.052

Critical issues and current status of SiC/SiC composites for fusion
journal, December 2000

Hasegawa, A.; Kohyama, A.; Jones, R. H.
Journal of Nuclear Materials, Vol. 283-287
DOI: 10.1016/S0022-3115(00)00374-3

Measurements of net erosion and redeposition of molybdenum in DIII-D
journal, July 2013

Wampler, W. R.; Stangeby, P. C.; Watkins, J. G.
Journal of Nuclear Materials, Vol. 438
DOI: 10.1016/j.jnucmat.2013.01.178

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
DOI: 10.1016/j.nme.2019.02.003

Net versus gross erosion of high- Z materials in the divertor of DIII-D
journal, April 2014

Rudakov, D. L.; Stangeby, P. C.; Wampler, W. R.
Physica Scripta, Vol. T159
DOI: 10.1088/0031-8949/2014/T159/014030

DiMES PMI research at DIII-D in support of ITER and beyond
journal, November 2017

Rudakov, D. L.; Abrams, T.; Ding, R.
Fusion Engineering and Design, Vol. 124
DOI: 10.1016/j.fusengdes.2017.03.007

Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion
journal, May 2015

Brooks, J. N.; Elder, J. D.; McLean, A. G.
Fusion Engineering and Design, Vol. 94
DOI: 10.1016/j.fusengdes.2015.03.022

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
DOI: 10.1088/1741-4326/aa66b2

Simulation of gross and net erosion of high- Z materials in the DIII-D divertor
journal, December 2015

Ding, R.; Stangeby, P. C.; Rudakov, D. L.
Nuclear Fusion, Vol. 56, Issue 1
DOI: 10.1088/0029-5515/56/1/016021

Characterization of wall conditions in DIII-D
journal, May 1997

Holtrop, K. L.; Jackson, G. L.; Kellman, A. G.
Journal of Vacuum Science & Technology A: Vacuum, Surfaces, and Films, Vol. 15, Issue 3
DOI: 10.1116/1.580800

Physical and chemical sputtering of graphite and SiC by hydrogen and helium in the energy range of 600 to 7500 eV
journal, December 1976

Roth, J.; Bohdansky, J.; Poschenrieder, W.
Journal of Nuclear Materials, Vol. 63
DOI: 10.1016/0022-3115(76)90330-5

The ARIES Advanced and Conservative Tokamak Power Plant Study
journal, January 2015

Kessel, C. E.; Tillack, M. S.; Najmabadi, F.
Fusion Science and Technology, Vol. 67, Issue 1
DOI: 10.13182/FST14-794

Recent progress in the development of SiC composites for nuclear fusion applications
journal, December 2018

Koyanagi, T.; Katoh, Y.; Nozawa, T.
Journal of Nuclear Materials, Vol. 511
DOI: 10.1016/j.jnucmat.2018.06.017

Similar Records in DOE PAGES and OSTI.GOV collections:

Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES

Journal Article Cappelli, L. ; Guterl, J. ; Fedorczak, N. ; ... - Nuclear Materials and Energy

An experiment was performed in the DIII-D lower divertor to validate numerical SOL tungsten (W) impurity erosion and redeposition simulations against experimental data. The net and gross erosion of W were calculated as a function of the voltage (or bias) applied to the exposed material. Five samples were inserted into the DIII-D lower divertor using the Divertor Material Evaluation System (DiMES) manipulator and exposed to constant L-mode attached plasma conditions. Each sample was partially coated with W. During plasma shots, samples were biased with respect to the machine vessel ground, ranging from -60 V to 25 V. The ERO2.0 codemore »« less
https://doi.org/10.1016/j.nme.2023.101551
Control of high-Z PFC erosion by local gas injection in DIII-D

Journal Article Rudakov, D. L. ; Stangeby, P. C. ; Wong, C. P. C. ; ... - Journal of Nuclear Materials

Reduced erosion of a high-Z PFC divertor surface was observed in DIII-D with local injection of methane and deuterium gases. Molybdenum-coated silicon samples were exposed in the lower divertor of DIII-D using DiMES under plasma conditions previously shown to cause significant net erosion of Mo. Three exposures with ¹³CH₄ and one exposure with D₂ gas injection about 12 cm upstream of the samples located within 1-2 cm of the attached strike point were performed. Reduction of Mo erosion was evidenced in-situ by the suppression of MoI line radiation at 386.4 nm once the gas injection started. Post-mortem ion beam analysismore »« less
https://doi.org/10.1016/j.jnucmat.2014.10.056
Divertor erosion in DIII-D

Conference Whyte, D G ; Bastasz, R ; Wampler, W R ; ...

Net erosion rates of carbon target plates have been measured in situ for the DIII-D lower divertor. The principal method of obtaining this data is the DiMES sample probe. Recent experiments have focused on erosion at the outer strike-point (OSP) of two divertor plasma conditions: attached (T{sub e} > 40 eV) ELMing plasmas, and detached (T{sub e} < 2 eV) ELMing plasmas. For the attached cases, the erosion rates exceed 10 cm/exposure-year, even with incident heat flux < 1 MW/m{sup 2}. In this case, measurements and modeling agree for both gross and net carbon erosion, showing the near-surface transport andmore »« less
https://doi.org/10.2172/654183

Full Text Available
Characterizing Low-Z erosion and deposition in the DIII-D divertor using aluminum

Journal Article Chrobak, C. P. ; Doerner, R. P. ; Stangeby, P. C. ; ... - Nuclear Materials and Energy

Here, we present measurements and modeling of aluminum erosion and redeposition experiments in separate helium and deuterium low power, low density L-mode plasmas at the outer divertor strike point of DIII-D to provide a low-Z material benchmark dataset for tokamak erosion-deposition modeling codes. Coatings of Al ~100nm thick were applied to ideal (smooth) and realistic (rough) surfaces and exposed to repeat plasma discharges using the DiMES probe. Redeposition and re-erosion in all cases was primarily in the downstream toroidal field direction, evident from both in-situ spectroscopic and post-mortem non spectroscopic measurements. The gross Al erosion yield estimated from both Hemore »« less
Cited by 4
https://doi.org/10.1016/j.nme.2016.11.033
Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion

Journal Article Wampler, William R. ; Brooks, J. N. ; Elder, J. D. ; ... - Fusion Engineering and Design

We analyze a DIII-D tokamak experiment where two tungsten spots on the removable DiMES divertor probe were exposed to 12 seconds of attached plasma conditions, with moderate strike point temperature and density (~20 eV, ~4.5x1019 m-3), and high carbon impurity content (~3%). “Small” (1 mm diameter) and “large” (1 cm dia.) deposited samples were used for assessing gross and net tungsten sputtering erosion. The analysis uses a 3-D erosion/redeposition code package (REDEP/WBC), with input from a diagnostic-calibrated near-surface plasma code (OEDGE), and with focus on charge state resolved impinging carbon ion flux and energy. The tungsten surfaces are primarily sputteredmore »« less
Cited by 23
https://doi.org/10.1016/j.fusengdes.2015.03.022

Full Text Available

Similar Records

Title: Net versus gross erosion of silicon carbide in DIII-D divertor

Abstract

Citation Formats

A design retrospective of the DIII-D tokamak journal, May 2002

Divertor materials evaluation system (DiMES) journal, October 1998

An experimental comparison of gross and net erosion of Mo in the DIII-D divertor journal, July 2013

Critical issues and current status of SiC/SiC composites for fusion journal, December 2000

Measurements of net erosion and redeposition of molybdenum in DIII-D journal, July 2013

Atomic insight into concurrent He, D, and T sputtering and near-surface implantation of 3C-SiC crystallographic surfaces journal, May 2019

Net versus gross erosion of high- Z materials in the divertor of DIII-D journal, April 2014

DiMES PMI research at DIII-D in support of ITER and beyond journal, November 2017

Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion journal, May 2015

The inter-ELM tungsten erosion profile in DIII-D H-mode discharges and benchmarking with ERO+OEDGE modeling journal, April 2017

Simulation of gross and net erosion of high- Z materials in the DIII-D divertor journal, December 2015

Characterization of wall conditions in DIII-D journal, May 1997

Physical and chemical sputtering of graphite and SiC by hydrogen and helium in the energy range of 600 to 7500 eV journal, December 1976

The ARIES Advanced and Conservative Tokamak Power Plant Study journal, January 2015

Recent progress in the development of SiC composites for nuclear fusion applications journal, December 2018

A design retrospective of the DIII-D tokamak
journal, May 2002

Divertor materials evaluation system (DiMES)
journal, October 1998

An experimental comparison of gross and net erosion of Mo in the DIII-D divertor
journal, July 2013

Critical issues and current status of SiC/SiC composites for fusion
journal, December 2000

Measurements of net erosion and redeposition of molybdenum in DIII-D
journal, July 2013

Atomic insight into concurrent He, D, and T sputtering and near-surface implantation of 3C-SiC crystallographic surfaces
journal, May 2019

Net versus gross erosion of high- Z materials in the divertor of DIII-D
journal, April 2014

DiMES PMI research at DIII-D in support of ITER and beyond
journal, November 2017

Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion
journal, May 2015

The inter-ELM tungsten erosion profile in DIII-D H-mode discharges and benchmarking with ERO+OEDGE modeling
journal, April 2017

Simulation of gross and net erosion of high- Z materials in the DIII-D divertor
journal, December 2015

Characterization of wall conditions in DIII-D
journal, May 1997

Physical and chemical sputtering of graphite and SiC by hydrogen and helium in the energy range of 600 to 7500 eV
journal, December 1976

The ARIES Advanced and Conservative Tokamak Power Plant Study
journal, January 2015

Recent progress in the development of SiC composites for nuclear fusion applications
journal, December 2018