Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion

Wampler, William R.; Brooks, J. N.; Elder, J. D.; McLean, Adam G.; Rudakov, Dmitry L.; Stangeby, Peter C.

doi:10.1016/j.fusengdes.2015.03.022

Title: Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion

Journal Article · Sun Mar 29 00:00:00 EDT 2015 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2015.03.022· OSTI ID:1184989

Wampler, William R. ^[1]; Brooks, J. N. ^[2]; Elder, J. D. ^[3]; McLean, Adam G. ^[4]; Rudakov, Dmitry L. ^[5]; Stangeby, Peter C. ^[3]

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)

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.

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Research Organization:: 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 Organization:: 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)

Grant/Contract Number:: AC04-94AL85000; AC52-07NA27344; FC02-04ER54698; FG02-07ER54917

OSTI ID:: 1184989

Alternate ID(s):: OSTI ID: 1305822; OSTI ID: 1376234

Report Number(s):: SAND-2014-20047J; LLNL-JRNL-698174; 547393; TRN: US1600628

Journal Information:: Fusion Engineering and Design, Vol. 94, Issue C; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 23 works

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References (15)

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Cited By (2)

Reduced model of high-Z impurity redeposition and erosion in tokamak divertor and its application to DIII-D experiments Guterl, J.; Wampler, W. R.; Rudakov, D. Plasma Physics and Controlled Fusion, Vol. 61, Issue 12 https://doi.org/10.1088/1361-6587/ab5144	journal	November 2019
Material testing facilities and programs for plasma-facing component testing Linsmeier, Ch.; Unterberg, B.; Coenen, J. W. Nuclear Fusion, Vol. 57, Issue 9 https://doi.org/10.1088/1741-4326/aa4feb	journal	June 2017

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