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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. Furthermore, these techniques may find applications in the future devices.

Authors:
 [1];  [2];  [3];  [2];  [4];  [5];  [1];  [6];  [7];  [8];  [1];  [2];  [1];  [9];  [4];  [10];  [3];  [11];  [1];  [10] more »;  [2];  [10];  [1];  [8];  [2];  [6];  [8];  [2] « less
  1. Univ. of California, San Diego, La Jolla, CA (United States)
  2. General Atomics, San Diego, CA (United States)
  3. Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  4. Univ. of Toronto Institute for Aerospace Studies, Toronto (Canada)
  5. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  6. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  7. Purdue Univ., West Lafayette, IN (United States)
  8. Sandia National Lab. (SNL-CA), Livermore, CA (United States)
  9. Univ. of Tennessee, Knoxville, TN (United States)
  10. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  11. Univ. of Wisconsin, Madison, WI (United States)
Publication Date:
Research Org.:
General Atomics, San Diego, CA (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC)
OSTI Identifier:
1375007
Alternate Identifier(s):
OSTI ID: 1483172; OSTI ID: 1497289; OSTI ID: 1550473
Report Number(s):
LLNL-JRNL-703329
Journal ID: ISSN 0920-3796; PII: S0920379617302107
Grant/Contract Number:  
FC02-04ER54698; AC05-00OR22725; AC52-07NA27344; FG02-07ER54917; AC05-06OR23100; DE AC05-00OR22725; AC04-94AL85000; GA-DE-SC0008698
Resource Type:
Accepted Manuscript
Journal Name:
Fusion Engineering and Design
Additional Journal Information:
Journal Volume: 124; Journal ID: ISSN 0920-3796
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; DIII-D tokamak; DiMES; Plasma-facing components; Plasma-material interactions

Citation Formats

Rudakov, Dimitry L., Abrams, Tyler, Ding, Rui, Guo, Houyang Y., Stangeby, Peter C., Wampler, William R., Boedo, Jose A., Briesemeister, Alexis R., Brooks, J. N., Buchenauer, Dean A., Bykov, Igor, Chrobak, Chris, Doerner, R. P., Donovan, David C., Elder, J. David, Fenstermacher, Max E., Guterl, Jerome, Hinson, Edward T., Hollmann, Eric M., Lasnier, Charles J., Leonard, Anthony W., McLean, Adam G., Moyer, Richard A., Nygren, R. E., Thomas, Dan M., Unterberg, Ezekial A., Watkins, Jonathan G., and Wong, C. P. C. DiMES PMI research at DIII-D in support of ITER and beyond. United States: N. p., 2017. Web. doi:10.1016/j.fusengdes.2017.03.007.
Rudakov, Dimitry L., Abrams, Tyler, Ding, Rui, Guo, Houyang Y., Stangeby, Peter C., Wampler, William R., Boedo, Jose A., Briesemeister, Alexis R., Brooks, J. N., Buchenauer, Dean A., Bykov, Igor, Chrobak, Chris, Doerner, R. P., Donovan, David C., Elder, J. David, Fenstermacher, Max E., Guterl, Jerome, Hinson, Edward T., Hollmann, Eric M., Lasnier, Charles J., Leonard, Anthony W., McLean, Adam G., Moyer, Richard A., Nygren, R. E., Thomas, Dan M., Unterberg, Ezekial A., Watkins, Jonathan G., & Wong, C. P. C. DiMES PMI research at DIII-D in support of ITER and beyond. United States. doi:10.1016/j.fusengdes.2017.03.007.
Rudakov, Dimitry L., Abrams, Tyler, Ding, Rui, Guo, Houyang Y., Stangeby, Peter C., Wampler, William R., Boedo, Jose A., Briesemeister, Alexis R., Brooks, J. N., Buchenauer, Dean A., Bykov, Igor, Chrobak, Chris, Doerner, R. P., Donovan, David C., Elder, J. David, Fenstermacher, Max E., Guterl, Jerome, Hinson, Edward T., Hollmann, Eric M., Lasnier, Charles J., Leonard, Anthony W., McLean, Adam G., Moyer, Richard A., Nygren, R. E., Thomas, Dan M., Unterberg, Ezekial A., Watkins, Jonathan G., and Wong, C. P. C. Mon . "DiMES PMI research at DIII-D in support of ITER and beyond". United States. doi:10.1016/j.fusengdes.2017.03.007. https://www.osti.gov/servlets/purl/1375007.
@article{osti_1375007,
title = {DiMES PMI research at DIII-D in support of ITER and beyond},
author = {Rudakov, Dimitry L. and Abrams, Tyler and Ding, Rui and Guo, Houyang Y. and Stangeby, Peter C. and Wampler, William R. and Boedo, Jose A. and Briesemeister, Alexis R. and Brooks, J. N. and Buchenauer, Dean A. and Bykov, Igor and Chrobak, Chris and Doerner, R. P. and Donovan, David C. and Elder, J. David and Fenstermacher, Max E. and Guterl, Jerome and Hinson, Edward T. and Hollmann, Eric M. and Lasnier, Charles J. and Leonard, Anthony W. and McLean, Adam G. and Moyer, Richard A. and Nygren, R. E. and Thomas, Dan M. and Unterberg, Ezekial A. and Watkins, Jonathan G. and Wong, C. P. C.},
abstractNote = {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. Furthermore, these techniques may find applications in the future devices.},
doi = {10.1016/j.fusengdes.2017.03.007},
journal = {Fusion Engineering and Design},
number = ,
volume = 124,
place = {United States},
year = {2017},
month = {3}
}

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Figures / Tables:

Figure 1 Figure 1: Experimental arrangement on DIII-D. Poloidal locations of DiMES, MiMES and main diagnostics are shown in (b). Locations of shelf LPs, DTS scattering volumes, W-coated TZM tiles, and OSP during W short-range transport experiment (see Section 4.6) are shown in (c).

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Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.