DiMES PMI research at DIII-D in support of ITER and beyond

DiMES and DIII-D teams

doi:10.1016/j.fusengdes.2017.03.007

DiMES PMI research at DIII-D in support of ITER and beyond

DiMES and DIII-D teams

Power Exhaust and Particle Control

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Abstract

An overview of recent Plasma-Material Interactions (PMI) research at the DIII-D tokamak using the Divertor Material Evaluation System (DiMES) is presented. The DiMES manipulator allows for exposure of material samples in the lower divertor of DIII-D under well-diagnosed ITER-relevant plasma conditions. Plasma parameters during the exposures are characterized by an extensive diagnostic suite including a number of spectroscopic diagnostics, Langmuir probes, IR imaging, and Divertor Thomson Scattering. Post-mortem measurements of net erosion/deposition on the samples are done by Ion Beam Analysis, and results are modelled by the ERO and REDEP/WBC codes with plasma background reproduced by OEDGE/DIVIMP modelling based on experimental inputs. This article highlights experiments studying sputtering erosion, re-deposition and migration of high-Z elements, mostly tungsten and molybdenum, as well as some alternative materials. Results are generally encouraging for use of high-Z PFCs in ITER and beyond, showing high redeposition and reduced net sputter erosion. Two methods of high-Z PFC surface erosion control, with (i) external electrical biasing and (ii) local gas injection, are also discussed. These techniques may find applications in the future devices.

Original language	English
Pages (from-to)	196-201
Number of pages	6
Journal	Fusion Engineering and Design
Volume	124
DOIs	https://doi.org/10.1016/j.fusengdes.2017.03.007
State	Published - Nov 2017

Funding

This work was supported in part by the US DOE under DE-FG02-07ER54917, DE-AC05-06OR23100, DE AC05-00OR22725, DE-FC02-04ER54698, DE-AC52-07NA27344, DE-AC04-94AL85000, GA-DE-SC0008698, and Collaborative Research Opportunities Grant from the National Sciences and Engineering Research Council of Canada. 1DIII-D1 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
U.S. Department of Energy	GA-DE-SC0008698, DE AC05-00OR22725, DE-AC04-94AL85000, DE-FC02-04ER54698, DE-AC52-07NA27344, DE-FG02-07ER54917, DE-AC05-06OR23100
Natural Sciences and Engineering Research Council of Canada

Keywords

DIII-D tokamak
DiMES
Plasma-facing components
Plasma-material interactions

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.fusengdes.2017.03.007

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@article{323e7f97cd44416ea97c047a8d9c19f9,

title = "DiMES PMI research at DIII-D in support of ITER and beyond",

abstract = "An overview of recent Plasma-Material Interactions (PMI) research at the DIII-D tokamak using the Divertor Material Evaluation System (DiMES) is presented. The DiMES manipulator allows for exposure of material samples in the lower divertor of DIII-D under well-diagnosed ITER-relevant plasma conditions. Plasma parameters during the exposures are characterized by an extensive diagnostic suite including a number of spectroscopic diagnostics, Langmuir probes, IR imaging, and Divertor Thomson Scattering. Post-mortem measurements of net erosion/deposition on the samples are done by Ion Beam Analysis, and results are modelled by the ERO and REDEP/WBC codes with plasma background reproduced by OEDGE/DIVIMP modelling based on experimental inputs. This article highlights experiments studying sputtering erosion, re-deposition and migration of high-Z elements, mostly tungsten and molybdenum, as well as some alternative materials. Results are generally encouraging for use of high-Z PFCs in ITER and beyond, showing high redeposition and reduced net sputter erosion. Two methods of high-Z PFC surface erosion control, with (i) external electrical biasing and (ii) local gas injection, are also discussed. These techniques may find applications in the future devices.",

keywords = "DIII-D tokamak, DiMES, Plasma-facing components, Plasma-material interactions",

author = "{DiMES and DIII-D teams} and Rudakov, {D. L.} and T. Abrams and R. Ding and Guo, {H. Y.} and Stangeby, {P. C.} and Wampler, {W. R.} and Boedo, {J. A.} and A. Briesemeister and Brooks, {J. N.} and Buchenauer, {D. A.} and I. Bykov and C. Chrobak and Doerner, {R. P.} and D. Donovan and Elder, {J. D.} and Fenstermacher, {M. E.} and J. Guterl and E. Hinson and Hollmann, {E. M.} and Lasnier, {C. J.} and Leonard, {A. W.} and McLean, {A. G.} and Moyer, {R. A.} and Nygren, {R. E.} and Thomas, {D. M.} and Unterberg, {E. A.} and Watkins, {J. G.} and Wong, {C. P.C.}",

note = "Publisher Copyright: {\textcopyright} 2017 Elsevier B.V.",

year = "2017",

month = nov,

doi = "10.1016/j.fusengdes.2017.03.007",

language = "English",

volume = "124",

pages = "196--201",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

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AU - DiMES and DIII-D teams

AU - Rudakov, D. L.

AU - Abrams, T.

AU - Ding, R.

AU - Guo, H. Y.

AU - Stangeby, P. C.

AU - Wampler, W. R.

AU - Boedo, J. A.

AU - Briesemeister, A.

AU - Brooks, J. N.

AU - Buchenauer, D. A.

AU - Bykov, I.

AU - Chrobak, C.

AU - Doerner, R. P.

AU - Donovan, D.

AU - Elder, J. D.

AU - Fenstermacher, M. E.

AU - Guterl, J.

AU - Hinson, E.

AU - Hollmann, E. M.

AU - Lasnier, C. J.

AU - Leonard, A. W.

AU - McLean, A. G.

AU - Moyer, R. A.

AU - Nygren, R. E.

AU - Thomas, D. M.

AU - Unterberg, E. A.

AU - Watkins, J. G.

AU - Wong, C. P.C.

PY - 2017/11

Y1 - 2017/11

N2 - An overview of recent Plasma-Material Interactions (PMI) research at the DIII-D tokamak using the Divertor Material Evaluation System (DiMES) is presented. The DiMES manipulator allows for exposure of material samples in the lower divertor of DIII-D under well-diagnosed ITER-relevant plasma conditions. Plasma parameters during the exposures are characterized by an extensive diagnostic suite including a number of spectroscopic diagnostics, Langmuir probes, IR imaging, and Divertor Thomson Scattering. Post-mortem measurements of net erosion/deposition on the samples are done by Ion Beam Analysis, and results are modelled by the ERO and REDEP/WBC codes with plasma background reproduced by OEDGE/DIVIMP modelling based on experimental inputs. This article highlights experiments studying sputtering erosion, re-deposition and migration of high-Z elements, mostly tungsten and molybdenum, as well as some alternative materials. Results are generally encouraging for use of high-Z PFCs in ITER and beyond, showing high redeposition and reduced net sputter erosion. Two methods of high-Z PFC surface erosion control, with (i) external electrical biasing and (ii) local gas injection, are also discussed. These techniques may find applications in the future devices.

AB - An overview of recent Plasma-Material Interactions (PMI) research at the DIII-D tokamak using the Divertor Material Evaluation System (DiMES) is presented. The DiMES manipulator allows for exposure of material samples in the lower divertor of DIII-D under well-diagnosed ITER-relevant plasma conditions. Plasma parameters during the exposures are characterized by an extensive diagnostic suite including a number of spectroscopic diagnostics, Langmuir probes, IR imaging, and Divertor Thomson Scattering. Post-mortem measurements of net erosion/deposition on the samples are done by Ion Beam Analysis, and results are modelled by the ERO and REDEP/WBC codes with plasma background reproduced by OEDGE/DIVIMP modelling based on experimental inputs. This article highlights experiments studying sputtering erosion, re-deposition and migration of high-Z elements, mostly tungsten and molybdenum, as well as some alternative materials. Results are generally encouraging for use of high-Z PFCs in ITER and beyond, showing high redeposition and reduced net sputter erosion. Two methods of high-Z PFC surface erosion control, with (i) external electrical biasing and (ii) local gas injection, are also discussed. These techniques may find applications in the future devices.

KW - DIII-D tokamak

KW - DiMES

KW - Plasma-facing components

KW - Plasma-material interactions

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U2 - 10.1016/j.fusengdes.2017.03.007

DO - 10.1016/j.fusengdes.2017.03.007

M3 - Article

AN - SCOPUS:85016079544

SN - 0920-3796

VL - 124

SP - 196

EP - 201

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

ER -

DiMES PMI research at DIII-D in support of ITER and beyond

Abstract

Funding

Keywords

UN SDGs

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