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Title: Determination of the characteristic magnetic pre-sheath length at divertor surfaces using micro-engineered targets on DiMES at DIII-D

Abstract

The magnetic pre-sheath (MPS) width, LMPS, is a critical parameter to define the sheath potential, which controls the ion trajectory of low-Z species (D, T, He, and C), as well as the prompt re-deposition of high-Z species. In this work, to determine LMPS, we fabricated micro-trenches (30×30×4 µm) via focused ion beam (FIB) milling on a silicon surface and exposed them to L-mode deuterium plasmas in DIII-D via the Divertor Material Evaluation System (DiMES) removable sample exposure probe. The areal distribution of impurity depositions, mainly consisting of carbon, was measured by energy-dispersive X-ray spectroscopy (EDS) to reveal the deuterium ion shadowing effect on the trench floors. The carbon deposition profiles showed that the erosion was maximized for the azimuthal direction of φ = -40° (referenced to the toroidal magnetic field direction) as well as the polar angle of θ = 80°. A Monte Carlo equation-of-motion model, based on a collisionless MPS, was used to calculate the azimuthal and polar deuterium ion angle distributions (IADs) for a range of LMPS = k × ρi, where ρi is the ion gyro radius and k = 0.5-4. Then, gross erosion profiles were calculated by a Monte Carlo micro-patterning and roughness (MPR) code formore » ion sputtering using as input the calculated azimuthal and polar IADs for each value of k. Good agreement with the experimental C deposition profiles was obtained for the case k = 2.5-3.5. This result is consistent with a previous kinetic modeling prediction of k ~ 3, as well as previous analytical investigations that predicted the LMPS to be several ion gyro radii. A validation of theoretical sheath models supports its applicability to ITER and pilot plant divertors to successfully predict plasma-materials interactions.« less

Authors:
ORCiD logo [1];  [2];  [3];  [4]; ORCiD logo [5]; ORCiD logo [6]; ORCiD logo [7];  [8]; ORCiD logo [3];  [8]; ORCiD logo [3];  [1]
  1. Princeton Univ., NJ (United States)
  2. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  3. General Atomics, San Diego, CA (United States)
  4. Rutgers Univ., Piscataway, NJ (United States)
  5. Univ. of Tennessee, Knoxville, TN (United States)
  6. ITER Organization, St. Paul Lez Durance (France)
  7. Univ. of California, San Diego, CA (United States)
  8. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Publication Date:
Research Org.:
General Atomics, San Diego, CA (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Science (SC), Advanced Scientific Computing Research (ASCR); National Science Foundation (NSF)
OSTI Identifier:
1832886
Grant/Contract Number:  
FC02-04ER54698; AC02-09CH11466; AC52-07NA27344; FG02-07ER54917; DMR-2011750
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 62; 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; Divertor; Sheath; Magnetic Pre-Sheath; Chodura Sheath; Ion Angle Distribution; Erosion; Deposition; DiMES; Plasma-Material Interaction; Surface Analysis

Citation Formats

Abe, Shota, Skinner, Charles, Bykov, Igor, Yeh, Yao-Wen, Lasa, Ane, Coburn, Jonathan, Rudakov, Dmitry L., Lasnier, Charles, Wang, H. Q., McLean, Adam G., Abrams, Tyler, and Koel, Bruce E. Determination of the characteristic magnetic pre-sheath length at divertor surfaces using micro-engineered targets on DiMES at DIII-D. United States: N. p., 2022. Web. doi:10.1088/1741-4326/ac3cdb.
Abe, Shota, Skinner, Charles, Bykov, Igor, Yeh, Yao-Wen, Lasa, Ane, Coburn, Jonathan, Rudakov, Dmitry L., Lasnier, Charles, Wang, H. Q., McLean, Adam G., Abrams, Tyler, & Koel, Bruce E. Determination of the characteristic magnetic pre-sheath length at divertor surfaces using micro-engineered targets on DiMES at DIII-D. United States. https://doi.org/10.1088/1741-4326/ac3cdb
Abe, Shota, Skinner, Charles, Bykov, Igor, Yeh, Yao-Wen, Lasa, Ane, Coburn, Jonathan, Rudakov, Dmitry L., Lasnier, Charles, Wang, H. Q., McLean, Adam G., Abrams, Tyler, and Koel, Bruce E. Mon . "Determination of the characteristic magnetic pre-sheath length at divertor surfaces using micro-engineered targets on DiMES at DIII-D". United States. https://doi.org/10.1088/1741-4326/ac3cdb. https://www.osti.gov/servlets/purl/1832886.
@article{osti_1832886,
title = {Determination of the characteristic magnetic pre-sheath length at divertor surfaces using micro-engineered targets on DiMES at DIII-D},
author = {Abe, Shota and Skinner, Charles and Bykov, Igor and Yeh, Yao-Wen and Lasa, Ane and Coburn, Jonathan and Rudakov, Dmitry L. and Lasnier, Charles and Wang, H. Q. and McLean, Adam G. and Abrams, Tyler and Koel, Bruce E.},
abstractNote = {The magnetic pre-sheath (MPS) width, LMPS, is a critical parameter to define the sheath potential, which controls the ion trajectory of low-Z species (D, T, He, and C), as well as the prompt re-deposition of high-Z species. In this work, to determine LMPS, we fabricated micro-trenches (30×30×4 µm) via focused ion beam (FIB) milling on a silicon surface and exposed them to L-mode deuterium plasmas in DIII-D via the Divertor Material Evaluation System (DiMES) removable sample exposure probe. The areal distribution of impurity depositions, mainly consisting of carbon, was measured by energy-dispersive X-ray spectroscopy (EDS) to reveal the deuterium ion shadowing effect on the trench floors. The carbon deposition profiles showed that the erosion was maximized for the azimuthal direction of φ = -40° (referenced to the toroidal magnetic field direction) as well as the polar angle of θ = 80°. A Monte Carlo equation-of-motion model, based on a collisionless MPS, was used to calculate the azimuthal and polar deuterium ion angle distributions (IADs) for a range of LMPS = k × ρi, where ρi is the ion gyro radius and k = 0.5-4. Then, gross erosion profiles were calculated by a Monte Carlo micro-patterning and roughness (MPR) code for ion sputtering using as input the calculated azimuthal and polar IADs for each value of k. Good agreement with the experimental C deposition profiles was obtained for the case k = 2.5-3.5. This result is consistent with a previous kinetic modeling prediction of k ~ 3, as well as previous analytical investigations that predicted the LMPS to be several ion gyro radii. A validation of theoretical sheath models supports its applicability to ITER and pilot plant divertors to successfully predict plasma-materials interactions.},
doi = {10.1088/1741-4326/ac3cdb},
journal = {Nuclear Fusion},
number = 6,
volume = 62,
place = {United States},
year = {Mon Apr 04 00:00:00 EDT 2022},
month = {Mon Apr 04 00:00:00 EDT 2022}
}

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