Modeling of inter- and intra-edge-localized mode tungsten erosion during DIII-D H-mode discharges

Xu, G. L.; Guterl, J.; Abrams, T.; Wang, H. Q.; Elder, J. D.; Unterberg, E. A.; Thomas, D. M.; Stangeby, P. C.; Guo, H. Y.; Ye, M. Y.

doi:10.1088/1741-4326/ab3e96

Modeling of inter- and intra-edge-localized mode tungsten erosion during DIII-D H-mode discharges

Journal Article · Fri Oct 04 00:00:00 EDT 2019 · Nuclear Fusion

DOI:https://doi.org/10.1088/1741-4326/ab3e96· OSTI ID:1577445

^[1]; ^[2]; Abrams, T. ^[3]; Wang, H. Q. ^[3]; Elder, J. D. ^[4]; Unterberg, E. A. ^[5]; Thomas, D. M. ^[3]; ^[6]; Guo, H. Y. ^[3]; Ye, M. Y. ^[7]

Univ. of Science and Technology of China, Hefei (China). School of Physical Science; Shenzhen Univ. (China). College of Physics and Optoelectronic Engineering; General Atomics, Energy & Advanced Concepts, DIII-D
Oak Ridge Associated Univ., Oak Ridge, TN (United States)
General Atomics, San Diego, CA (United States)
Univ. of Toronto (Canada). Inst. for Aerospace Studies
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
General Atomics, San Diego, CA (United States); Univ. of Toronto (Canada). Inst. for Aerospace Studies
Univ. of Science and Technology of China, Hefei (China). School of Physical Science

The relationship between the tungsten gross erosion and the ELM characteristics is investigated for high performance (H-mode) discharges during the dedicated Metal Rings Campaign in DIII-D, using the one-dimensional ‘free-streaming’ ELM model, coupled to a simple analytical TRIM.SP sputtering model, while the OEDGE code is employed to calculate the inter-ELM impurity distribution and tungsten gross erosion. A carbon-tungsten mixed target material is used for both inter- and intra-ELM simulations. The OEDGE results reveal that the inter-ELM tungsten gross erosion rate is not sensitive to the carbon fraction on the tungsten surface layer; a wider range of carbon fractions from 0.3 to 0.6 give similar tungsten gross erosion profiles and match the diagnostic data, which is consistent with the simple analytical model. However, the intra-ELM simulation indicates that the value of surface carbon fraction can be as low as 0.3 to reproduce the measured tungsten gross erosion during ELMs, based on the effective ionizations/photon (S/XB) value of WI emissions. Finally, for both inter- and intra-ELM cases, carbon is predicted to dominate the tungsten erosion. However, in contrast to the inter-ELM tungsten erosion, which is dominated by locally redeposited C²⁺, the energetic C⁶⁺ originating from the pedestal can contribute substantial tungsten erosion in the near-separatrix region during ELMs, and the width of this C⁶⁺ dominated region exhibits a negative correlation with the heat flux density carried by ELMs.

View Accepted Manuscript (DOE)

Research Organization:: General Atomics, San Diego, CA (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)

Grant/Contract Number:: FC02-04ER54698; SC0018423

OSTI ID:: 1577445

Alternate ID(s):: OSTI ID: 1813258
OSTI ID: 22930032

Journal Information:: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 12 Vol. 59; ISSN 0029-5515

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

References (28)

Interpretive modeling of simple-as-possible-plasma discharges on DIII-D using the OEDGE code Stangeby, P. C.; Elder, J. D.; Boedo, J. A. Journal of Nuclear Materials, Vol. 313-316 https://doi.org/10.1016/S0022-3115(02)01470-8	journal	March 2003
Calculation of observable quantities using a divertor impurity interpretive code, DIVIMP Stangeby, P. C.; Elder, J. D. Journal of Nuclear Materials, Vol. 196-198 https://doi.org/10.1016/S0022-3115(06)80042-5	journal	December 1992
Divertor materials evaluation system at DIII-D Wong, C. P. C.; Junge, R.; Phelps, R. D. Journal of Nuclear Materials, Vol. 196-198 https://doi.org/10.1016/S0022-3115(06)80159-5	journal	December 1992
Simulation of ion beam sputtering with SDTrimSP, TRIDYN and SRIM Hofsäss, H.; Zhang, K.; Mutzke, A. Applied Surface Science, Vol. 310 https://doi.org/10.1016/j.apsusc.2014.03.152	journal	August 2014
Carbon impurity behavior on plasma facing surface of tungsten Ueda, Y.; Fukumoto, M.; Sawamura, I. Fusion Engineering and Design, Vol. 81, Issue 1-7 https://doi.org/10.1016/j.fusengdes.2005.08.047	journal	February 2006
ITER tungsten divertor design development and qualification program Hirai, T.; Escourbiac, F.; Carpentier-Chouchana, S. Fusion Engineering and Design, Vol. 88, Issue 9-10 https://doi.org/10.1016/j.fusengdes.2013.05.010	journal	October 2013
Carbon behavior on tungsten surface after carbon and hydrogen mixed beam irradiation Shimada, T.; Funabiki, T.; Kawakami, R. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.180	journal	August 2004
A conceptual model of the magnetic topology and nonlinear dynamics of ELMs Evans, T. E.; Yu, J. H.; Jakubowski, M. W. Journal of Nuclear Materials, Vol. 390-391 https://doi.org/10.1016/j.jnucmat.2009.01.209	journal	June 2009
Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade Dux, R.; Bobkov, V.; Herrmann, A. Journal of Nuclear Materials, Vol. 390-391 https://doi.org/10.1016/j.jnucmat.2009.01.225	journal	June 2009
Plasma-surface interaction in the Be/W environment: Conclusions drawn from the JET-ILW for ITER Brezinsek, S. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.12.007	journal	August 2015
Experimental validation of a model for particle recycling and tungsten erosion during ELMs in the DIII-D divertor Abrams, T.; Unterberg, E. A.; McLean, A. G. Nuclear Materials and Energy, Vol. 17 https://doi.org/10.1016/j.nme.2018.10.011	journal	December 2018
Study of DIII-D tungsten erosion processes by using a carbon–tungsten mixed material model Xu, G. L.; Guterl, J.; Abrams, T. Nuclear Materials and Energy, Vol. 18 https://doi.org/10.1016/j.nme.2018.12.020	journal	January 2019
Infrared thermography of the DIII‐D divertor targets Hill, D. N.; Ellis, R.; Ferguson, W. Review of Scientific Instruments, Vol. 59, Issue 8 https://doi.org/10.1063/1.1140040	journal	August 1988
High heat flux Langmuir probe array for the DIII-D divertor plates Watkins, J. G.; Taussig, D.; Boivin, R. L. Review of Scientific Instruments, Vol. 79, Issue 10 https://doi.org/10.1063/1.2982423	journal	October 2008
Initial results of the high resolution edge Thomson scattering upgrade at DIII-D Eldon, D.; Bray, B. D.; Deterly, T. M. Review of Scientific Instruments, Vol. 83, Issue 10 https://doi.org/10.1063/1.4738656	journal	October 2012
Improved edge charge exchange recombination spectroscopy in DIII-D Chrystal, C.; Burrell, K. H.; Grierson, B. A. Review of Scientific Instruments, Vol. 87, Issue 11 https://doi.org/10.1063/1.4958915	journal	August 2016
Impurity retention by divertors. I. One dimensional models Stangeby, P. C.; Elder, J. D. Nuclear Fusion, Vol. 35, Issue 11 https://doi.org/10.1088/0029-5515/35/11/I06	journal	November 1995
Calculation and experimental test of the cooling factor of tungsten Pütterich, T.; Neu, R.; Dux, R. Nuclear Fusion, Vol. 50, Issue 2 https://doi.org/10.1088/0029-5515/50/2/025012	journal	January 2010
The Chodura sheath for angles of a few degrees between the magnetic field and the surface of divertor targets and limiters Stangeby, P. C. Nuclear Fusion, Vol. 52, Issue 8 https://doi.org/10.1088/0029-5515/52/8/083012	journal	July 2012
ELM-resolved divertor erosion in the JET ITER-Like Wall Den Harder, N.; Brezinsek, S.; Pütterich, T. Nuclear Fusion, Vol. 56, Issue 2 https://doi.org/10.1088/0029-5515/56/2/026014	journal	January 2016
A model of ELM filament energy evolution due to parallel losses Fundamenski, W.; Pitts, R. A.; contributors, Jet Efda Plasma Physics and Controlled Fusion, Vol. 48, Issue 1 https://doi.org/10.1088/0741-3335/48/1/008	journal	December 2005
Quasineutral plasma expansion into infinite vacuum as a model for parallel ELM transport Moulton, D.; Ghendrih, Ph; Fundamenski, W. Plasma Physics and Controlled Fusion, Vol. 55, Issue 8 https://doi.org/10.1088/0741-3335/55/8/085003	journal	May 2013
Ion target impact energy during Type I edge localized modes in JET ITER-like Wall Guillemaut, C.; Jardin, A.; Horacek, J. Plasma Physics and Controlled Fusion, Vol. 57, Issue 8 https://doi.org/10.1088/0741-3335/57/8/085006	journal	July 2015
The inter-ELM tungsten erosion profile in DIII-D H-mode discharges and benchmarking with ERO+OEDGE modeling Abrams, T.; Ding, R.; Guo, H. Y. Nuclear Fusion, Vol. 57, Issue 5 https://doi.org/10.1088/1741-4326/aa66b2	journal	April 2017
Experimental validation of an analytical kinetic model for edge-localized modes in JET-ITER-like wall Guillemaut, C.; Metzger, C.; Moulton, D. Nuclear Fusion, Vol. 58, Issue 6 https://doi.org/10.1088/1741-4326/aab7b1	journal	April 2018
Inter-ELM Power Decay Length for JET and ASDEX Upgrade: Measurement and Comparison with Heuristic Drift-Based Model Eich, T.; Sieglin, B.; Scarabosio, A. Physical Review Letters, Vol. 107, Issue 21 https://doi.org/10.1103/PhysRevLett.107.215001	journal	November 2011
Advances in Low-Temperature Tungsten Spectroscopy Capability to Quantify DIII-D Divertor Erosion Abrams, Tyler; Thomas, Daniel M.; Unterberg, Ezekial A. IEEE Transactions on Plasma Science, Vol. 46, Issue 5 https://doi.org/10.1109/tps.2018.2797691	journal	May 2018
Dynamic Behavior of Tungsten Surfaces due to Simultaneous Impact of Hydrogen and Carbon Ion Beam Kawakami, Retsuo; Shimada, Tomohisa; Ueda, Yoshio Japanese Journal of Applied Physics, Vol. 42, Issue Part 1, No. 12 https://doi.org/10.1143/JJAP.42.7529	journal	December 2003

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70 PLASMA PHYSICS AND FUSION TECHNOLOGY
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Modeling of inter- and intra-edge-localized mode tungsten erosion during DIII-D H-mode discharges

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