High-Z material erosion and its control in DIII-D carbon divertor

R. Ding; D. L. Rudakov; P. C. Stangeby; W. R. Wampler; T. Abrams; S. Brezinsek; A. Briesemeister; I. Bykov; V. S. Chan; C. P. Chrobak; J. D. Elder; H. Y. Guo; J. Guterl; A. Kirschner; C. J. Lasnier; A. W. Leonard; M. A. Makowski; A. G. McLean; P. B. Snyder; D. M. Thomas; D. Tskhakaya; E. A. Unterberg; H. Q. Wang; J. G. Watkins

doi:10.1016/j.nme.2017.03.012

High-Z material erosion and its control in DIII-D carbon divertor

R. Ding, D. L. Rudakov, P. C. Stangeby, W. R. Wampler, T. Abrams, S. Brezinsek, A. Briesemeister, I. Bykov, V. S. Chan, C. P. Chrobak, J. D. Elder, H. Y. Guo, J. Guterl, A. Kirschner, C. J. Lasnier, A. W. Leonard, M. A. Makowski, A. G. McLean, P. B. Snyder, D. M. ThomasD. Tskhakaya, E. A. Unterberg, H. Q. Wang, J. G. Watkins

Power Exhaust and Particle Control

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

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Abstract

As High-Z materials will likely be used as plasma-facing components (PFCs) in future fusion devices, the erosion of high-Z materials is a key issue for high-power, long pulse operation. High-Z material erosion and redeposition have been studied using tungsten and molybdenum coated samples exposed in well-diagnosed DIII-D divertor plasma discharges. By coupling dedicated experiments and modelling using the 3D Monte Carlo code ERO, the roles of sheath potential and background carbon impurities in determining high-Z material erosion are identified. Different methods suggested by modelling have been investigated to control high-Z material erosion in DIII-D experiments. The erosion of Mo and W is found to be strongly suppressed by local injection of methane and deuterium gases. The ¹³C deposition resulting from local ¹³CH₄ injection also provides information on radial transport due to E × B drifts and cross field diffusion. Finally, D₂ gas puffing is found to cause local plasma perturbation, suppressing W erosion because of the lower effective sputtering yield of W at lower plasma temperature and for higher carbon concentration in the mixed surface layer.

Original language	English
Pages (from-to)	247-252
Number of pages	6
Journal	Nuclear Materials and Energy
Volume	12
DOIs	https://doi.org/10.1016/j.nme.2017.03.012
State	Published - Aug 2017

Funding

This material is based upon work supported by the US Department of Energy, Office of Science, Office of Fusion Energy Sciences and Office of Advanced Scientific Computing Research through the Scientific Discovery through Advanced Computing (SciDAC) project on Plasma-Surface Interactions, under Award No. GA-DE-SC0008698, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Awards DE-AC05-06OR23100, DE-FG02-07ER54917, DE-AC05-00OR22725, DE-FC02-04ER54698, and DE-AC52-07NA27344. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the US Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. The first author acknowledges the supports by the National Magnetic Confinement Fusion Science Program of China under contract No 2013GB107004 , the National Natural Science Foundation of China under Contract No 11375010 , 11675218 and the Sino-German Centre for Research Promotion under Contract No GZ769 . 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 . This material is based upon work supported by the US Department of Energy, Office of Science, Office of Fusion Energy Sciences and Office of Advanced Scientific Computing Research through the Scientific Discovery through Advanced Computing (SciDAC) project on Plasma-Surface Interactions, under Award No. GA-DE-SC0008698, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Awards DE-AC05-06OR23100, DE-FG02-07ER54917, DE-AC05-00OR22725, DE-FC02-04ER54698, and DE-AC52-07NA27344. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the US Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. The first author acknowledges the supports by the National Magnetic Confinement Fusion Science Program of China under contract No 2013GB107004, the National Natural Science Foundation of China under Contract No 11375010, 11675218 and the Sino-German Centre for Research Promotion under Contract No GZ769. 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.

Funders	Funder number
DIII-D National Fusion Facility
DOE Office of Science user facility	DE-AC05-00OR22725, DE-FC02-04ER54698, DE-AC52-07NA27344, DE-FG02-07ER54917, DE-AC05-06OR23100
Office of Fusion Energy Sciences and Office of Advanced Scientific Computing Research	GA-DE-SC0008698
Sandia Corporation
Sino-German Centre for Research Promotion	GZ769
US Department of Energy
US Department of Energy's National Nuclear Security Administration	DE-AC04-94AL85000
Lockheed Martin Corporation
Office of Science
Advanced Scientific Computing Research
Fusion Energy Sciences
Sandia National Laboratories
National Natural Science Foundation of China	11675218, 11375010
National Magnetic Confinement Fusion Program of China	2013GB107004

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Ding, R., Rudakov, D. L., Stangeby, P. C., Wampler, W. R., Abrams, T., Brezinsek, S., Briesemeister, A., Bykov, I., Chan, V. S., Chrobak, C. P., Elder, J. D., Guo, H. Y., Guterl, J., Kirschner, A., Lasnier, C. J., Leonard, A. W., Makowski, M. A., McLean, A. G., Snyder, P. B., ... Watkins, J. G. (2017). High-Z material erosion and its control in DIII-D carbon divertor. Nuclear Materials and Energy, 12, 247-252. https://doi.org/10.1016/j.nme.2017.03.012

@article{b6802b37772e41e9beeff97e9bcfd030,

title = "High-Z material erosion and its control in DIII-D carbon divertor",

abstract = "As High-Z materials will likely be used as plasma-facing components (PFCs) in future fusion devices, the erosion of high-Z materials is a key issue for high-power, long pulse operation. High-Z material erosion and redeposition have been studied using tungsten and molybdenum coated samples exposed in well-diagnosed DIII-D divertor plasma discharges. By coupling dedicated experiments and modelling using the 3D Monte Carlo code ERO, the roles of sheath potential and background carbon impurities in determining high-Z material erosion are identified. Different methods suggested by modelling have been investigated to control high-Z material erosion in DIII-D experiments. The erosion of Mo and W is found to be strongly suppressed by local injection of methane and deuterium gases. The 13C deposition resulting from local 13CH4 injection also provides information on radial transport due to E × B drifts and cross field diffusion. Finally, D2 gas puffing is found to cause local plasma perturbation, suppressing W erosion because of the lower effective sputtering yield of W at lower plasma temperature and for higher carbon concentration in the mixed surface layer.",

author = "R. Ding and Rudakov, {D. L.} and Stangeby, {P. C.} and Wampler, {W. R.} and T. Abrams and S. Brezinsek and A. Briesemeister and I. Bykov and Chan, {V. S.} and Chrobak, {C. P.} and Elder, {J. D.} and Guo, {H. Y.} and J. Guterl and A. Kirschner and Lasnier, {C. J.} and Leonard, {A. W.} and Makowski, {M. A.} and McLean, {A. G.} and Snyder, {P. B.} and Thomas, {D. M.} and D. Tskhakaya and Unterberg, {E. A.} and Wang, {H. Q.} and Watkins, {J. G.}",

note = "Publisher Copyright: {\textcopyright} 2017 The Authors",

year = "2017",

month = aug,

doi = "10.1016/j.nme.2017.03.012",

language = "English",

volume = "12",

pages = "247--252",

journal = "Nuclear Materials and Energy",

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Ding, R, Rudakov, DL, Stangeby, PC, Wampler, WR, Abrams, T, Brezinsek, S, Briesemeister, A, Bykov, I, Chan, VS, Chrobak, CP, Elder, JD, Guo, HY, Guterl, J, Kirschner, A, Lasnier, CJ, Leonard, AW, Makowski, MA, McLean, AG, Snyder, PB, Thomas, DM, Tskhakaya, D, Unterberg, EA, Wang, HQ & Watkins, JG 2017, 'High-Z material erosion and its control in DIII-D carbon divertor', Nuclear Materials and Energy, vol. 12, pp. 247-252. https://doi.org/10.1016/j.nme.2017.03.012

TY - JOUR

T1 - High-Z material erosion and its control in DIII-D carbon divertor

AU - Ding, R.

AU - Rudakov, D. L.

AU - Stangeby, P. C.

AU - Wampler, W. R.

AU - Abrams, T.

AU - Brezinsek, S.

AU - Briesemeister, A.

AU - Bykov, I.

AU - Chan, V. S.

AU - Chrobak, C. P.

AU - Elder, J. D.

AU - Guo, H. Y.

AU - Guterl, J.

AU - Kirschner, A.

AU - Lasnier, C. J.

AU - Leonard, A. W.

AU - Makowski, M. A.

AU - McLean, A. G.

AU - Snyder, P. B.

AU - Thomas, D. M.

AU - Tskhakaya, D.

AU - Unterberg, E. A.

AU - Wang, H. Q.

AU - Watkins, J. G.

PY - 2017/8

Y1 - 2017/8

N2 - As High-Z materials will likely be used as plasma-facing components (PFCs) in future fusion devices, the erosion of high-Z materials is a key issue for high-power, long pulse operation. High-Z material erosion and redeposition have been studied using tungsten and molybdenum coated samples exposed in well-diagnosed DIII-D divertor plasma discharges. By coupling dedicated experiments and modelling using the 3D Monte Carlo code ERO, the roles of sheath potential and background carbon impurities in determining high-Z material erosion are identified. Different methods suggested by modelling have been investigated to control high-Z material erosion in DIII-D experiments. The erosion of Mo and W is found to be strongly suppressed by local injection of methane and deuterium gases. The 13C deposition resulting from local 13CH4 injection also provides information on radial transport due to E × B drifts and cross field diffusion. Finally, D2 gas puffing is found to cause local plasma perturbation, suppressing W erosion because of the lower effective sputtering yield of W at lower plasma temperature and for higher carbon concentration in the mixed surface layer.

AB - As High-Z materials will likely be used as plasma-facing components (PFCs) in future fusion devices, the erosion of high-Z materials is a key issue for high-power, long pulse operation. High-Z material erosion and redeposition have been studied using tungsten and molybdenum coated samples exposed in well-diagnosed DIII-D divertor plasma discharges. By coupling dedicated experiments and modelling using the 3D Monte Carlo code ERO, the roles of sheath potential and background carbon impurities in determining high-Z material erosion are identified. Different methods suggested by modelling have been investigated to control high-Z material erosion in DIII-D experiments. The erosion of Mo and W is found to be strongly suppressed by local injection of methane and deuterium gases. The 13C deposition resulting from local 13CH4 injection also provides information on radial transport due to E × B drifts and cross field diffusion. Finally, D2 gas puffing is found to cause local plasma perturbation, suppressing W erosion because of the lower effective sputtering yield of W at lower plasma temperature and for higher carbon concentration in the mixed surface layer.

UR - http://www.scopus.com/inward/record.url?scp=85015296197&partnerID=8YFLogxK

U2 - 10.1016/j.nme.2017.03.012

DO - 10.1016/j.nme.2017.03.012

M3 - Article

AN - SCOPUS:85015296197

SN - 2352-1791

VL - 12

SP - 247

EP - 252

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

ER -

High-Z material erosion and its control in DIII-D carbon divertor

Abstract

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