DiMES PMI research at DIII-D in support of ITER and beyond

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.

doi:10.1016/j.fusengdes.2017.03.007

DiMES PMI research at DIII-D in support of ITER and beyond

Journal Article · Mon Mar 27 00:00:00 EDT 2017 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2017.03.007· OSTI ID:1375007

Rudakov, Dimitry L. ^[1]; Abrams, Tyler ^[2]; Ding, Rui ^[3]; Guo, Houyang Y. ^[2]; Stangeby, Peter C. ^[4]; Wampler, William R. ^[5]; Boedo, Jose A. ^[6]; Briesemeister, Alexis R. ^[7]; Brooks, J. N. ^[8]; Buchenauer, Dean A. ^[9]; Bykov, Igor ^[6]; Chrobak, Chris ^[2]; Doerner, R. P. ^[6]; Donovan, David C. ^[10]; Elder, J. David ^[4]; Fenstermacher, Max E. ^[11]; Guterl, Jerome ^[3]; Hinson, Edward T. ^[12]; Hollmann, Eric M. ^[6]; Lasnier, Charles J. ^[11] more »

Univ. of California, San Diego, La Jolla, CA (United States); General Atomics
General Atomics, San Diego, CA (United States)
Oak Ridge Associated Univ., Oak Ridge, TN (United States)
Univ. of Toronto Institute for Aerospace Studies, Toronto (Canada)
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Univ. of California, San Diego, La Jolla, CA (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Purdue Univ., West Lafayette, IN (United States)
Sandia National Lab. (SNL-CA), Livermore, CA (United States)
Univ. of Tennessee, Knoxville, TN (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Univ. of Wisconsin, Madison, WI (United States)

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.

View Accepted Manuscript (DOE)

Research Organization:: General Atomics, San Diego, CA (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: FC02-04ER54698

OSTI ID:: 1375007

Alternate ID(s):: OSTI ID: 1550473
OSTI ID: 22737812
OSTI ID: 1483172
OSTI ID: 1497289

Journal Information:: Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Vol. 124; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (29)

Elastic and inelastic surface effects on ion penetration and the resulting sputtering and backscattering Hassanein, A. M.; Smith, D. L. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 13, Issue 1-3 https://doi.org/10.1016/0168-583X(86)90507-0	journal	March 1986
Interpretive modeling of simple-as-possible-plasma discharges on DIII-D using the OEDGE code Stangeby, P. C.; Elder, J. D.; Boedo, J. A. Journal of Nuclear Materials, Vol. 313-316 https://doi.org/10.1016/S0022-3115(02)01470-8	journal	March 2003
Divertor materials evaluation system at DIII-D Wong, C. P. C.; Junge, R.; Phelps, R. D. Journal of Nuclear Materials, Vol. 196-198 https://doi.org/10.1016/S0022-3115(06)80159-5	journal	December 1992
Migration of tungsten eroded from divertor tiles in ASDEX Upgrade Krieger, K. Journal of Nuclear Materials, Vol. 241-243, Issue 1 https://doi.org/10.1016/S0022-3115(96)00596-X	journal	February 1997
In-situ deposition of silicon on the leading edge of the ALT-II limiter in TEXTOR-94 Mank, G. Journal of Nuclear Materials, Vol. 241-243, Issue 1 https://doi.org/10.1016/S0022-3115(96)00613-7	journal	February 1997
Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion Brooks, J. N.; Elder, J. D.; McLean, A. G. Fusion Engineering and Design, Vol. 94 https://doi.org/10.1016/j.fusengdes.2015.03.022	journal	May 2015
Study of local carbon transport on graphite, tungsten and molybdenum test limiters in TEXTOR by 13CH4 tracer injection Kreter, A.; Wienhold, P.; Borodin, D. Journal of Nuclear Materials, Vol. 363-365 https://doi.org/10.1016/j.jnucmat.2007.01.054	journal	June 2007
Deposition and re-erosion studies by means of local impurity injection in TEXTOR Kirschner, A.; Kreter, A.; Wienhold, P. Journal of Nuclear Materials, Vol. 415, Issue 1 https://doi.org/10.1016/j.jnucmat.2010.10.058	journal	August 2011
Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET van Rooij, G. J.; Coenen, J. W.; Aho-Mantila, L. Journal of Nuclear Materials, Vol. 438 https://doi.org/10.1016/j.jnucmat.2013.01.007	journal	July 2013
An experimental comparison of gross and net erosion of Mo in the DIII-D divertor Stangeby, P. C.; Rudakov, D. L.; Wampler, W. R. Journal of Nuclear Materials, Vol. 438 https://doi.org/10.1016/j.jnucmat.2013.01.052	journal	July 2013
Control of high-Z PFC erosion by local gas injection in DIII-D Rudakov, D. L.; Stangeby, P. C.; Wong, C. P. C. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.10.056	journal	August 2015
Measurements of gross erosion of Al in the DIII-D divertor Chrobak, C.; Stangeby, P. C.; Leonard, A. W. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.11.003	journal	August 2015
Interpretation of plasma impurity deposition probes. Analytic approximation Stangeby, P. C. Physics of Fluids, Vol. 30, Issue 10 https://doi.org/10.1063/1.866502	journal	January 1987
Impurity retention by divertors. I. One dimensional models Stangeby, P. C.; Elder, J. D. Nuclear Fusion, Vol. 35, Issue 11 https://doi.org/10.1088/0029-5515/35/11/I06	journal	November 1995
Simulation of the plasma-wall interaction in a tokamak with the Monte Carlo code ERO-TEXTOR Kirschner, A.; Philipps, V.; Winter, J. Nuclear Fusion, Vol. 40, Issue 5 https://doi.org/10.1088/0029-5515/40/5/311	journal	May 2000
A design retrospective of the DIII-D tokamak Luxon, J. L. Nuclear Fusion, Vol. 42, Issue 5 https://doi.org/10.1088/0029-5515/42/5/313	journal	May 2002
The effect of thermo-oxidation on plasma performance and in-vessel components in DIII-D Davis, J. W.; Allen, S. L.; Fitzpatrick, B. W. N. Nuclear Fusion, Vol. 53, Issue 7 https://doi.org/10.1088/0029-5515/53/7/073008	journal	May 2013
ICRF operation with improved antennas in ASDEX Upgrade with W wall Bobkov, V.; Balden, M.; Bilato, R. Nuclear Fusion, Vol. 53, Issue 9 https://doi.org/10.1088/0029-5515/53/9/093018	journal	August 2013
Plasma-facing material alternatives to tungsten Brooks, J. N.; El-Guebaly, L.; Hassanein, A. Nuclear Fusion, Vol. 55, Issue 4 https://doi.org/10.1088/0029-5515/55/4/043002	journal	March 2015
Simulation of gross and net erosion of high- Z materials in the DIII-D divertor Ding, R.; Stangeby, P. C.; Rudakov, D. L. Nuclear Fusion, Vol. 56, Issue 1 https://doi.org/10.1088/0029-5515/56/1/016021	journal	December 2015
Interaction of adhered metallic dust with transient plasma heat loads Ratynskaia, S.; Tolias, P.; Bykov, I. Nuclear Fusion, Vol. 56, Issue 6 https://doi.org/10.1088/0029-5515/56/6/066010	journal	May 2016
Overview of the recent DiMES and MiMES experiments in DIII-D Rudakov, D. L.; Wong, C. P. C.; Litnovsky, A. Physica Scripta, Vol. T138 https://doi.org/10.1088/0031-8949/2009/T138/014007	journal	December 2009
Net versus gross erosion of high- Z materials in the divertor of DIII-D Rudakov, D. L.; Stangeby, P. C.; Wampler, W. R. Physica Scripta, Vol. T159 https://doi.org/10.1088/0031-8949/2014/T159/014030	journal	April 2014
Investigation of He–W interactions using DiMES on DIII-D Doerner, R. P.; Rudakov, D. L.; Chrobak, C. P. Physica Scripta, Vol. T167 https://doi.org/10.1088/0031-8949/T167/1/014054	journal	January 2016
Exposures of tungsten nanostructures to divertor plasmas in DIII-D Rudakov, D. L.; Wong, C. P. C.; Doerner, R. P. Physica Scripta, Vol. T167 https://doi.org/10.1088/0031-8949/T167/1/014055	journal	January 2016
The tungsten divertor experiment at ASDEX Upgrade Neu, R.; Asmussen, K.; Krieger, K. Plasma Physics and Controlled Fusion, Vol. 38, Issue 12A https://doi.org/10.1088/0741-3335/38/12A/013	journal	December 1996
Spectroscopic measurements of tungsten erosion in the ASDEX Upgrade divertor Thoma, A.; Asmussen, K.; Dux, R. Plasma Physics and Controlled Fusion, Vol. 39, Issue 9 https://doi.org/10.1088/0741-3335/39/9/014	journal	September 1997
Determination of the tungsten divertor retention at ASDEX Upgrade using a sublimation probe Geier, A.; Maier, H.; Neu, R. Plasma Physics and Controlled Fusion, Vol. 44, Issue 10 https://doi.org/10.1088/0741-3335/44/10/302	journal	September 2002
Measurements of Mo I S/XB values Nishijima, D.; Doerner, R. P.; Whyte, D. G. Journal of Physics B: Atomic, Molecular and Optical Physics, Vol. 43, Issue 22 https://doi.org/10.1088/0953-4075/43/22/225701	journal	October 2010

Cited By (3)

Utilization of outer-midplane collector probes with isotopically enriched tungsten tracer particles for impurity transport studies in the scrape-off layer of DIII-D (invited) Donovan, D. C.; Unterberg, E. A.; Stangeby, P. C. Review of Scientific Instruments, Vol. 89, Issue 10 https://doi.org/10.1063/1.5039347	journal	October 2018
Tungsten erosion by unipolar arcing in DIII-D Bykov, I.; Chrobak, C. P.; Abrams, T. Physica Scripta, Vol. T170 https://doi.org/10.1088/1402-4896/aa8e34	journal	October 2017
Localized divertor leakage measurements using isotopic tungsten sources during edge-localized mode-y H-mode discharges on DIII-D Unterberg, E. A.; Abrams, T.; Bykov, I. Nuclear Fusion, Vol. 60, Issue 1 https://doi.org/10.1088/1741-4326/ab537b	journal	November 2019