Recent DIII-D progress toward validating models of tungsten erosion, re-deposition, and migration for application to next-step fusion devices

Abrams, T.; Guterl, J. G.; Abe, S.; Donovan, D. C.; Bykov, I.; Johnson, Curt A.; Nichols, Jake H.; Elder, J. D.; Ennis, D. A.; Loch, S. D.; Rudakov, D. L.; Sinclair, G.; Skinner, C. H.; Stangeby, P. C.; Thomas, D. M.; Unterberg, Ezekial A.; Wampler, W. R.

doi:10.1088/2053-1591/ad0f43

Title: Recent DIII-D progress toward validating models of tungsten erosion, re-deposition, and migration for application to next-step fusion devices

Journal Article · 06 December 2023 · Materials Research Express (Online)

DOI: https://doi.org/10.1088/2053-1591/ad0f43 · OSTI ID:2228992

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General Atomics, San Diego, CA (United States)
Princeton University, NJ (United States); Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
University of Tennessee, Knoxville, TN (United States)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Auburn University, AL (United States)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
University of Toronto Institute for Aerospace Studies (Canada)
Auburn University, AL (United States)
University of California San Diego, La Jolla, CA (United States)
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

Fundamental mechanisms governing the erosion and prompt re-deposition of tungsten impurities in tokamak divertors are identified and analyzed to inform the lifetime of tungsten plasma-facing components in ITER and other future devices. Various experiments conducted at DIII-D to benchmark predictive models are presented, leveraging the DiMES removable sample exposure probe capability and the Metal Rings Campaign, in which toroidally symmetric rows of tungsten-coated tiles were installed in the DIII-D divertor. In tokamak divertors, the width of the electric sheath is of the order of the main ion Larmor radius, and a vast majority of sputtered tungsten impurities are typically ionized within the sheath. Therefore, W prompt redeposition is mainly governed by the ratio of the characteristic ionization mean-free path of neutral tungsten to the width of the sheath. In-situ monitoring of the prompt redeposition of tungsten impurities in divertors is demonstrated via the use of WII/WI line ratios and the ionizations/photon (S/XB) method in L-mode discharges. Even with this relatively limited set of emission measurements, net erosion measurements were found to be a consistent upper bound to an analytic scaling based on the ratio of the W ionization length, λ_iz and the width of the magnetic sheath rather than the ratio of λ_iz and the W⁺ gyro-radius. In the far-scrape-off layer (SOL) of the ITER divertor, however, it is calculated that the measurement of photon emissions associated with the ionization of tungsten impurities up to W⁵⁺ may be required. Finally, W deposition patterns on DiMES collector probes, interpreted via DIVIMP-WallDYN modelling, reveal the key roles of progressive W erosion/re-deposition staps and E × B drifts in regulating long-range high-Z material migration.

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Research Organization:: General Atomics, San Diego, CA (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE; USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC) Fusion Energy Sciences (FES); USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF); USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC02-09CH11466; AC05-00OR22725; FC02-04ER54698; FG02-07ER54917; FG02-95ER54309; NA0003525; SC0015877; SC0018423; SC0019256; SC0019308

OSTI ID:: 2228992

Journal Information:: Materials Research Express (Online), Journal Name: Materials Research Express (Online) Journal Issue: 12 Vol. 10; ISSN 2053-1591

Publisher:: IOP PublishingCopyright Statement

Country of Publication:: United States

Language:: English

References (50)

Modelling of Impurity Transport and Plasma-Wall Interaction in Fusion Devices with the ERO Code: Basics of the Code and Examples of Application: Modelling of Impurity Transport and Plasma-Wall Interaction in Fusion Devices with the ERO Code: Basics of the Code and Examples of Application Kirschner, A.; Tskhakaya, D.; Kawamura, G. Contributions to Plasma Physics, Vol. 56, Issue 6-8 https://doi.org/10.1002/ctpp.201610014	journal	July 2016
Effects of the Chodura sheath on tungsten ionization and emission in tokamak divertors Guterl, J.; Johnson, C.; Ennis, D. Contributions to Plasma Physics, Vol. 60, Issue 5-6 https://doi.org/10.1002/ctpp.201900140	journal	November 2019
Kinetic Theory Analysis of Sheaths and Shocks Ryutov, D. D. Contributions to Plasma Physics, Vol. 36, Issue 2-3 https://doi.org/10.1002/ctpp.2150360221	journal	January 1996
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
Study of gross and net erosion in the ASDEX Upgrade divertor Krieger, K. Journal of Nuclear Materials, Vol. 241-243, Issue 1 https://doi.org/10.1016/S0022-3115(96)00587-9	journal	February 1997
IMPGYRO: The full-orbit impurity transport code for SOL/divertor and its successful application to tungsten impurities Yamoto, Shohei; Homma, Yuki; Hoshino, Kazuo Computer Physics Communications, Vol. 248 https://doi.org/10.1016/j.cpc.2019.106979	journal	March 2020
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
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
Modelling of tungsten re-deposition coefficient Tskhakaya, D.; Groth, M. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.10.086	journal	August 2015
Assessment of tungsten sources in the edge plasma of WEST Marandet, Y.; Bufferand, H.; Bucalossi, J. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.11.030	journal	August 2015
ERO and PIC simulations of gross and net erosion of tungsten in the outer strike-point region of ASDEX Upgrade Hakola, A.; Airila, M. I.; Mellet, N. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2016.09.012	journal	August 2017
Experimentally-based ExB drifts in the DIII-D divertor and SOL calculated from integration of Ohm's law using Thomson scattering measurements of Te and ne Stangeby, P. C.; Elder, J. D.; McLean, A. G. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2017.03.021	journal	August 2017
ColRadPy: A Python collisional radiative solver Johnson, C. A.; Loch, S. D.; Ennis, D. A. Nuclear Materials and Energy, Vol. 20 https://doi.org/10.1016/j.nme.2019.01.013	journal	August 2019
Use of isotopic tungsten tracers and a stable-isotope-mixing model to characterize divertor source location in the DIII-D metal rings campaign Unterberg, E. A.; Donovan, D. C.; Duran, J. D. Nuclear Materials and Energy, Vol. 19 https://doi.org/10.1016/j.nme.2019.02.028	journal	May 2019
On the prediction and monitoring of tungsten prompt redeposition in tokamak divertors Guterl, J.; Bykov, I.; Ding, R. Nuclear Materials and Energy, Vol. 27 https://doi.org/10.1016/j.nme.2021.100948	journal	June 2021
Experimental verification of ion impact angle distribution at divertor surfaces using micro-engineered targets on DiMES at DIII-D Abe, S.; Skinner, C. H.; Bykov, I. Nuclear Materials and Energy, Vol. 27 https://doi.org/10.1016/j.nme.2021.100965	journal	June 2021
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
Plasma–wall transition in an oblique magnetic field Chodura, R. Physics of Fluids, Vol. 25, Issue 9 https://doi.org/10.1063/1.863955	journal	January 1982
The Design and Use of Tungsten Coated TZM Molybdenum Tile Inserts in the DIII-D Tokamak Divertor Holtrop, K.; Buchenauer, D.; Chrobak, C. Fusion Science and Technology, Vol. 72, Issue 4 https://doi.org/10.1080/15361055.2017.1347456	journal	August 2017
Tungsten as target material in fusion devices Naujoks, D.; Asmussen, K.; Bessenrodt-Weberpals, M. Nuclear Fusion, Vol. 36, Issue 6 https://doi.org/10.1088/0029-5515/36/6/I01	journal	June 1996
Calculation and experimental test of the cooling factor of tungsten Pütterich, T.; Neu, R.; Dux, R. Nuclear Fusion, Vol. 50, Issue 2 https://doi.org/10.1088/0029-5515/50/2/025012	journal	January 2010
The Chodura sheath for angles of a few degrees between the magnetic field and the surface of divertor targets and limiters Stangeby, P. C. Nuclear Fusion, Vol. 52, Issue 8 https://doi.org/10.1088/0029-5515/52/8/083012	journal	July 2012
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
Status and physics basis of the ITER divertor Pitts, R. A.; Kukushkin, A.; Loarte, A. Physica Scripta, Vol. T138 https://doi.org/10.1088/0031-8949/2009/T138/014001	journal	December 2009
Quantification of tungsten sputtering at W/C twin limiters in TEXTOR with the aid of local WF ₆ injection Brezinsek, S.; Borodin, D.; Coenen, J. W. Physica Scripta, Vol. T145 https://doi.org/10.1088/0031-8949/2011/T145/014016	journal	December 2011
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
Gross and net erosion of tungsten in the outer strike-point region of ASDEX Upgrade Hakola, A.; Airila, M. I.; Karhunen, J. Physica Scripta, Vol. T167 https://doi.org/10.1088/0031-8949/T167/1/014026	journal	January 2016
Spectroscopic determination of impurity influx from localized surfaces Behringer, K.; Summers, H. P.; Denne, B. Plasma Physics and Controlled Fusion, Vol. 31, Issue 14 https://doi.org/10.1088/0741-3335/31/14/001	journal	December 1989
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
Monte Carlo simulations of tungsten redeposition at the divertor target Chankin, A. V.; Coster, D. P.; Dux, R. Plasma Physics and Controlled Fusion, Vol. 56, Issue 2 https://doi.org/10.1088/0741-3335/56/2/025003	journal	January 2014
Kinetic simulations of the Chodura and Debye sheaths for magnetic fields with grazing incidence Coulette, David; Manfredi, Giovanni Plasma Physics and Controlled Fusion, Vol. 58, Issue 2 https://doi.org/10.1088/0741-3335/58/2/025008	journal	January 2016
Determination of rate coefficients for fusion-relevant atoms and molecules by modelling and measurement in the boundary layer of TEXTOR Pospieszczyk, A.; Borodin, D.; Brezinsek, S. Journal of Physics B: Atomic, Molecular and Optical Physics, Vol. 43, Issue 14 https://doi.org/10.1088/0953-4075/43/14/144017	journal	July 2010
Tungsten erosion by impurities and redeposition: focus on the magnetised sheath Mellet, N.; Gunn, J. P.; Pégourié, B. Plasma Physics and Controlled Fusion, Vol. 59, Issue 3 https://doi.org/10.1088/1361-6587/aa576c	journal	February 2017
Modelling of plasma-wall interaction and impurity transport in fusion devices and prompt deposition of tungsten as application Kirschner, A.; Tskhakaya, D.; Brezinsek, S. Plasma Physics and Controlled Fusion, Vol. 60, Issue 1 https://doi.org/10.1088/1361-6587/aa8dce	journal	November 2017
Advances in neutral tungsten ultraviolet spectroscopy for the potential benefit to gross erosion diagnosis Johnson, C. A.; Ennis, D. A.; Loch, S. D. Plasma Physics and Controlled Fusion, Vol. 61, Issue 9 https://doi.org/10.1088/1361-6587/ab2b25	journal	August 2019
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
The effect of metastable atomic levels in neutral tungsten for erosion and impurity transport applications Johnson, C. A.; Loch, S. D.; Ennis, D. A. Plasma Physics and Controlled Fusion, Vol. 62, Issue 12 https://doi.org/10.1088/1361-6587/abc08b	journal	November 2020
Measurements of tungsten migration in the DIII-D divertor Wampler, W. R.; Rudakov, D. L.; Watkins, J. G. Physica Scripta, Vol. T170 https://doi.org/10.1088/1402-4896/aa8d5a	journal	October 2017
First efforts in numerical modeling of tungsten migration in WEST with SolEdge2D-EIRENE and ERO2.0 Gallo, A.; Sepetys, A.; Romazanov, J. Physica Scripta, Vol. T171 https://doi.org/10.1088/1402-4896/ab4308	journal	January 2020
The inter-ELM tungsten erosion profile in DIII-D H-mode discharges and benchmarking with ERO+OEDGE modeling Abrams, T.; Ding, R.; Guo, H. Y. Nuclear Fusion, Vol. 57, Issue 5 https://doi.org/10.1088/1741-4326/aa66b2	journal	April 2017
Measurement and modeling of aluminum sputtering and ionization in the DIII-D divertor including magnetic pre-sheath effects Chrobak, C. P.; Stangeby, P. C.; Hollmann, E. Nuclear Fusion, Vol. 58, Issue 10 https://doi.org/10.1088/1741-4326/aad4c9	journal	August 2018
Erosion, screening, and migration of tungsten in the JET divertor Brezinsek, S.; Kirschner, A.; Mayer, M. Nuclear Fusion, Vol. 59, Issue 9 https://doi.org/10.1088/1741-4326/ab2aef	journal	August 2019
Modeling of inter- and intra-edge-localized mode tungsten erosion during DIII-D H-mode discharges Xu, G. L.; Guterl, J.; Abrams, T. Nuclear Fusion, Vol. 59, Issue 12 https://doi.org/10.1088/1741-4326/ab3e96	journal	October 2019
ERO modeling and analysis of tungsten erosion and migration from a toroidally symmetric source in the DIII-D divertor Guterl, J.; Abrams, T.; Johnson, C. A. Nuclear Fusion, Vol. 60, Issue 1 https://doi.org/10.1088/1741-4326/ab4c54	journal	November 2019
Modeling of ExB effects on tungsten re-deposition and transport in the DIII-D divertor Nichols, J. H.; Abrams, T.; Chrobak, C. P. Nuclear Fusion, Vol. 61, Issue 9 https://doi.org/10.1088/1741-4326/ac14e6	journal	August 2021
Determination of the characteristic magnetic pre-sheath length at divertor surfaces using micro-engineered targets on DiMES at DIII-D Abe, S.; Skinner, C. H.; Bykov, I. Nuclear Fusion, Vol. 62, Issue 6 https://doi.org/10.1088/1741-4326/ac3cdb	journal	April 2022
Time-dependent collisional radiative modeling of tungsten in the magnetic sheath for erosion diagnosis Johnson, C. A.; Ennis, D. A.; Loch, S. D. Nuclear Fusion, Vol. 63, Issue 9 https://doi.org/10.1088/1741-4326/ace3d9	journal	August 2023
Dirac R -matrix calculations for the electron-impact excitation of neutral tungsten providing noninvasive diagnostics for magnetic confinement fusion Smyth, R. T.; Ballance, C. P.; Ramsbottom, C. A. Physical Review A, Vol. 97, Issue 5 https://doi.org/10.1103/PhysRevA.97.052705	journal	May 2018
Advances in Low-Temperature Tungsten Spectroscopy Capability to Quantify DIII-D Divertor Erosion Abrams, Tyler; Thomas, Daniel M.; Unterberg, Ezekial A. IEEE Transactions on Plasma Science, Vol. 46, Issue 5 https://doi.org/10.1109/TPS.2018.2797691	journal	May 2018

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70 PLASMA PHYSICS AND FUSION TECHNOLOGY
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re-deposition
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tokamak
tungsten

Title: Recent DIII-D progress toward validating models of tungsten erosion, re-deposition, and migration for application to next-step fusion devices

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