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Title: 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:
 [1];  [2];  [3];  [4];  [5];  [3]
+ Show Author Affiliations
  1. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  2. Purdue Univ., West Lafayette, IN (United States)
  3. Univ. of Toronto Institute for Aerospace Studies, Toronto (Canada)
  4. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  5. 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.
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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
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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.
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@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}
}
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Journal Article:
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Publisher's Version of Record
https://doi.org/10.1016/j.fusengdes.2015.03.022
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Cited by: 23 works
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Works referenced in this record:

Modelling and analysis of DIII-D/DiMES sputtered impurity transport experiments
journal, April 1999

An experimental comparison of gross and net erosion of Mo in the DIII-D divertor
journal, July 2013

Advanced simulation of mixed-material erosion/evolution and application to low and high-Z containing plasma facing components
journal, July 2013

Net versus gross erosion of high- Z materials in the divertor of DIII-D
journal, April 2014

Tungsten as target material in fusion devices
journal, June 1996

Spectroscopic measurements of tungsten erosion in the ASDEX Upgrade divertor
journal, September 1997

Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade
journal, June 2009

Plasma–surface interaction issues of an all-metal ITER
journal, February 2009

Modelling of tungsten re-deposition coefficient
journal, August 2015

OEDGE modeling of 13C deposition in the inner divertor of DIII-D
journal, March 2005

Re-construction of detached divertor plasma conditions in DIII-D using spectroscopic and probe data
journal, March 2005

Modeling of sputtering erosion/redeposition—status and implications for fusion design
journal, July 2002

Dynamic analysis and evolution of mixed materials bombarded with multiple ions beams
journal, September 2010

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    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
    • DOI: 10.1088/1361-6587/ab5144

    Material testing facilities and programs for plasma-facing component testing
    journal, June 2017

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