Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion
Abstract
We analyze a DIII-D tokamak experiment where two tungsten spots on the removable DiMES divertor probe were exposed to 12 seconds of attached plasma conditions, with moderate strike point temperature and density (~20 eV, ~4.5x1019 m-3), and high carbon impurity content (~3%). “Small” (1 mm diameter) and “large” (1 cm dia.) deposited samples were used for assessing gross and net tungsten sputtering erosion. The analysis uses a 3-D erosion/redeposition code package (REDEP/WBC), with input from a diagnostic-calibrated near-surface plasma code (OEDGE), and with focus on charge state resolved impinging carbon ion flux and energy. The tungsten surfaces are primarily sputtered by the carbon, in charge states +1 to +4. We predict high redeposition (~75%) of sputtered tungsten on the 1 cm spot—with consequent reduced net erosion—and this agrees well with post-exposure DiMES probe RBS analysis data. This study and recent related work is encouraging for erosion lifetime and non-contamination performance of tokamak reactor high-Z plasma facing components.
- Authors:
-
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Purdue Univ., West Lafayette, IN (United States)
- Univ. of Toronto Institute for Aerospace Studies, Toronto (Canada)
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Univ. of California, San Diego, CA (United States)
- Publication Date:
- Research Org.:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); General Atomics, San Diego, CA (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-4); USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE National Nuclear Security Administration (NNSA)
- OSTI Identifier:
- 1184989
- Alternate Identifier(s):
- OSTI ID: 1305822; OSTI ID: 1376234
- Report Number(s):
- SAND-2014-20047J; LLNL-JRNL-698174
Journal ID: ISSN 0920-3796; 547393; TRN: US1600628
- Grant/Contract Number:
- AC04-94AL85000; AC52-07NA27344; FC02-04ER54698; FG02-07ER54917
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Fusion Engineering and Design
- Additional Journal Information:
- Journal Volume: 94; Journal Issue: C; Journal ID: ISSN 0920-3796
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; sputtering; erosion/redeposition; tungsten divertor; plasma material interaction modeling; 70 PLASMA PHYSICS AND FUSION
Citation Formats
Wampler, William R., Brooks, J. N., Elder, J. D., McLean, Adam G., Rudakov, Dmitry L., and Stangeby, Peter C. Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion. United States: N. p., 2015.
Web. doi:10.1016/j.fusengdes.2015.03.022.
Wampler, William R., Brooks, J. N., Elder, J. D., McLean, Adam G., Rudakov, Dmitry L., & Stangeby, Peter C. Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion. United States. https://doi.org/10.1016/j.fusengdes.2015.03.022
Wampler, William R., Brooks, J. N., Elder, J. D., McLean, Adam G., Rudakov, Dmitry L., and Stangeby, Peter C. Sun .
"Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion". United States. https://doi.org/10.1016/j.fusengdes.2015.03.022. https://www.osti.gov/servlets/purl/1184989.
@article{osti_1184989,
title = {Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion},
author = {Wampler, William R. and Brooks, J. N. and Elder, J. D. and McLean, Adam G. and Rudakov, Dmitry L. and Stangeby, Peter C.},
abstractNote = {We analyze a DIII-D tokamak experiment where two tungsten spots on the removable DiMES divertor probe were exposed to 12 seconds of attached plasma conditions, with moderate strike point temperature and density (~20 eV, ~4.5x1019 m-3), and high carbon impurity content (~3%). “Small” (1 mm diameter) and “large” (1 cm dia.) deposited samples were used for assessing gross and net tungsten sputtering erosion. The analysis uses a 3-D erosion/redeposition code package (REDEP/WBC), with input from a diagnostic-calibrated near-surface plasma code (OEDGE), and with focus on charge state resolved impinging carbon ion flux and energy. The tungsten surfaces are primarily sputtered by the carbon, in charge states +1 to +4. We predict high redeposition (~75%) of sputtered tungsten on the 1 cm spot—with consequent reduced net erosion—and this agrees well with post-exposure DiMES probe RBS analysis data. This study and recent related work is encouraging for erosion lifetime and non-contamination performance of tokamak reactor high-Z plasma facing components.},
doi = {10.1016/j.fusengdes.2015.03.022},
journal = {Fusion Engineering and Design},
number = C,
volume = 94,
place = {United States},
year = {Sun Mar 29 00:00:00 EDT 2015},
month = {Sun Mar 29 00:00:00 EDT 2015}
}
Web of Science
Works referenced in this record:
Modelling and analysis of DIII-D/DiMES sputtered impurity transport experiments
journal, April 1999
- Brooks, J. N.; Whyte, D. G.
- Nuclear Fusion, Vol. 39, Issue 4
An experimental comparison of gross and net erosion of Mo in the DIII-D divertor
journal, July 2013
- Stangeby, P. C.; Rudakov, D. L.; Wampler, W. R.
- Journal of Nuclear Materials, Vol. 438
Advanced simulation of mixed-material erosion/evolution and application to low and high-Z containing plasma facing components
journal, July 2013
- Brooks, J. N.; Hassanein, A.; Sizyuk, T.
- Journal of Nuclear Materials, Vol. 438
Net versus gross erosion of high- Z materials in the divertor of DIII-D
journal, April 2014
- Rudakov, D. L.; Stangeby, P. C.; Wampler, W. R.
- Physica Scripta, Vol. T159
Analysis of tungsten migration from the C-MOD divertor; prediction of high redeposition rate, and code validation progress
journal, March 2013
- Brooks, J. N.
- Nuclear Fusion, Vol. 53, Issue 4
Tungsten as target material in fusion devices
journal, June 1996
- Naujoks, D.; Asmussen, K.; Bessenrodt-Weberpals, M.
- Nuclear Fusion, Vol. 36, Issue 6
Spectroscopic measurements of tungsten erosion in the ASDEX Upgrade divertor
journal, September 1997
- Thoma, A.; Asmussen, K.; Dux, R.
- Plasma Physics and Controlled Fusion, Vol. 39, Issue 9
Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade
journal, June 2009
- Dux, R.; Bobkov, V.; Herrmann, A.
- Journal of Nuclear Materials, Vol. 390-391
Plasma–surface interaction issues of an all-metal ITER
journal, February 2009
- Brooks, J. N.; Allain, J. P.; Doerner, R. P.
- Nuclear Fusion, Vol. 49, Issue 3
Modelling of tungsten re-deposition coefficient
journal, August 2015
- Tskhakaya, D.; Groth, M.
- Journal of Nuclear Materials, Vol. 463
OEDGE modeling of 13C deposition in the inner divertor of DIII-D
journal, March 2005
- Elder, J. D.; Stangeby, P. C.; Whyte, D. G.
- Journal of Nuclear Materials, Vol. 337-339
Re-construction of detached divertor plasma conditions in DIII-D using spectroscopic and probe data
journal, March 2005
- Lisgo, S.; Stangeby, P. C.; Elder, J. D.
- Journal of Nuclear Materials, Vol. 337-339
Modeling of sputtering erosion/redeposition—status and implications for fusion design
journal, July 2002
- Brooks, Jeffrey N.
- Fusion Engineering and Design, Vol. 60, Issue 4
Dynamic analysis and evolution of mixed materials bombarded with multiple ions beams
journal, September 2010
- Sizyuk, T.; Hassanein, A.
- Journal of Nuclear Materials, Vol. 404, Issue 1
Scientific and Computational Challenges in Coupled Plasma Edge/Plasma-Material Interactions for Fusion Tokamaks: Scientific and Computational Challenges in Coupled Plasma Edge/Plasma-Material Interactions for Fusion Tokamaks
journal, June 2014
- Brooks, J. N.; Hassanein, A.; Koniges, A.
- Contributions to Plasma Physics, Vol. 54, Issue 4-6
Works referencing / citing this record:
Reduced model of high-Z impurity redeposition and erosion in tokamak divertor and its application to DIII-D experiments
journal, November 2019
- Guterl, J.; Wampler, W. R.; Rudakov, D.
- Plasma Physics and Controlled Fusion, Vol. 61, Issue 12
Material testing facilities and programs for plasma-facing component testing
journal, June 2017
- Linsmeier, Ch.; Unterberg, B.; Coenen, J. W.
- Nuclear Fusion, Vol. 57, Issue 9