Study of the impact of resonant magnetic perturbation fields on gross tungsten erosion using DiMES samples in DIII-D

Hinson, E. T.; Schmitz, O.; Frerichs, H.; Abrams, T.; Briesemeister, A.; Rudakov, D. L.; Unterberg, E. A.; Wampler, W. R.; Watkins, J. G.; Wang, H. Q.

doi:10.1088/1402-4896/aa9002

Title: Study of the impact of resonant magnetic perturbation fields on gross tungsten erosion using DiMES samples in DIII-D

Abstract

An experiment was conducted in DIII-D to compare gross tungsten (W) erosion on samples exposed to outer strike point (OSP) sweeps in L-mode plasmas for three conditions. These included two phases of resonant magnetic perturbations (RMPs), and a set with no perturbations. Upon RMP application, lobe structures indicative of strike point splitting of the OSP were evident in divertor camera data and on Langmuir probes. Gross W erosion flux, GW, inferred spectroscopically using the S/XB method applied to the 400.9 nm W-I line, was generally in the range Gamma(W)/Gamma(D+),(perpendicular to) = 2 x 10(-4) referenced to incident deuterium ion flux Gamma(D+),(perpendicular to) and was increased in the RMP cases by no more than 30% of the level observed in unperturbed discharges. A large reduction in gross erosion (50%) was observed in the private flux region at the W sample for one specific toroidal phase of the RMP field.

Authors:

^[1]; Schmitz, O. ^[1];

^[1];

^[2];

^[3]; Rudakov, D. L. ^[4];

^[3]; Wampler, W. R. ^[5]; Watkins, J. G. ^[5]; Wang, H. Q. ^[6]

Univ. of Wisconsin, Madison, WI (United States)
General Atomics, San Diego, CA (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of California, San Diego, CA (United States)
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Oak Ridge Associated Univ., Oak Ridge, TN (United States)

Publication Date:: Fri Oct 27 00:00:00 EDT 2017

Research Org.:: Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sandia National Laboratories, San Diego, CA (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

OSTI Identifier:: 1477318

Alternate Identifier(s):: OSTI ID: 1531250

Report Number(s):: SAND-2018-10785J
Journal ID: ISSN 0031-8949; 668321

Grant/Contract Number:: AC04-94AL85000; AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Physica Scripta

Additional Journal Information:: Journal Volume: T170; Journal ID: ISSN 0031-8949

Publisher:: IOP Publishing

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY

Citation Formats


                    Hinson, E. T., Schmitz, O., Frerichs, H., Abrams, T., Briesemeister, A., Rudakov, D. L., Unterberg, E. A., Wampler, W. R., Watkins, J. G., and Wang, H. Q. Study of the impact of resonant magnetic perturbation fields on gross tungsten erosion using DiMES samples in DIII-D.  United States: N. p., 2017. 
Web.  doi:10.1088/1402-4896/aa9002.

Copy to clipboard


                    Hinson, E. T., Schmitz, O., Frerichs, H., Abrams, T., Briesemeister, A., Rudakov, D. L., Unterberg, E. A., Wampler, W. R., Watkins, J. G., & Wang, H. Q. Study of the impact of resonant magnetic perturbation fields on gross tungsten erosion using DiMES samples in DIII-D.  United States.  https://doi.org/10.1088/1402-4896/aa9002

Copy to clipboard


                    Hinson, E. T., Schmitz, O., Frerichs, H., Abrams, T., Briesemeister, A., Rudakov, D. L., Unterberg, E. A., Wampler, W. R., Watkins, J. G., and Wang, H. Q. Fri .  
"Study of the impact of resonant magnetic perturbation fields on gross tungsten erosion using DiMES samples in DIII-D".  United States.  https://doi.org/10.1088/1402-4896/aa9002.  https://www.osti.gov/servlets/purl/1477318.

Copy to clipboard


                    
@article{osti_1477318,

  title        = {Study of the impact of resonant magnetic perturbation fields on gross tungsten erosion using DiMES samples in DIII-D},

  author       = {Hinson, E. T. and Schmitz, O. and Frerichs, H. and Abrams, T. and Briesemeister, A. and Rudakov, D. L. and Unterberg, E. A. and Wampler, W. R. and Watkins, J. G. and Wang, H. Q.},

  abstractNote = {An experiment was conducted in DIII-D to compare gross tungsten (W) erosion on samples exposed to outer strike point (OSP) sweeps in L-mode plasmas for three conditions. These included two phases of resonant magnetic perturbations (RMPs), and a set with no perturbations. Upon RMP application, lobe structures indicative of strike point splitting of the OSP were evident in divertor camera data and on Langmuir probes. Gross W erosion flux, GW, inferred spectroscopically using the S/XB method applied to the 400.9 nm W-I line, was generally in the range Gamma(W)/Gamma(D+),(perpendicular to) = 2 x 10(-4) referenced to incident deuterium ion flux Gamma(D+),(perpendicular to) and was increased in the RMP cases by no more than 30% of the level observed in unperturbed discharges. A large reduction in gross erosion (50%) was observed in the private flux region at the W sample for one specific toroidal phase of the RMP field.},

  doi          = {10.1088/1402-4896/aa9002},

  journal      = {Physica Scripta},

  number       = ,

  volume       = T170,

  place        = {United States},

  year         = {Fri Oct 27 00:00:00 EDT 2017},

  month        = {Fri Oct 27 00:00:00 EDT 2017}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1088/1402-4896/aa9002

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 1 work

Citation information provided by
Web of Science

Figures / Tables:

Figure 1: a.) Cross-section of the DIII-D tokamak divertor region, including an example connection length (L_c) plot of a discharge from this work, and the DiMES diagnostic suite’s OSP access. b.) Heat flux plot example showing modulated heat flux pattern due to RMP applications obtained with EMC3-EIRENE.

All figures and tables (5 total)

Save / Share:

Export Metadata

Save to My Library

Figures / Tables found in this record:

Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.

Similar Records in DOE PAGES and OSTI.GOV collections:

Divertor erosion in DIII-D

Conference Whyte, D G ; Bastasz, R ; Wampler, W R ; ...

Net erosion rates of carbon target plates have been measured in situ for the DIII-D lower divertor. The principal method of obtaining this data is the DiMES sample probe. Recent experiments have focused on erosion at the outer strike-point (OSP) of two divertor plasma conditions: attached (T{sub e} > 40 eV) ELMing plasmas, and detached (T{sub e} < 2 eV) ELMing plasmas. For the attached cases, the erosion rates exceed 10 cm/exposure-year, even with incident heat flux < 1 MW/m{sup 2}. In this case, measurements and modeling agree for both gross and net carbon erosion, showing the near-surface transport andmore »« less
https://doi.org/10.2172/654183

Full Text Available
Predicting tungsten erosion and leakage properties for the new V-shaped small angle slot divertor in DIII-D

Journal Article Sinclair, G. ; Maurizio, R. ; Ma, X. ; ... - Nuclear Fusion

Impurity transport modeling of the new tungsten (W)-coated, V-shaped small angle slot (SAS) divertor in the DIII-D tokamak was conducted using the SOLPS-ITER plasma edge code package and the DIVIMP impurity tracking code. The inboard baffle of the current SAS divertor will be shifted closer to the outboard baffle, creating a V-corner at the slot vertex. In addition, the outboard baffle will be coated with 10–15 μm of W for experiments studying high-Z sourcing and leakage in a closed divertor. Modeling of the 'SAS-VW' divertor predicts that these changes to the inner baffle will reduce W gross erosion by 40×more »« less
https://doi.org/10.1088/1741-4326/ac8b95

Full Text Available
The effectiveness of D ₂ pellet injection in reducing intra-ELM and inter-ELM tungsten divertor erosion rates in DIII-D during the Metal Rings Campaign

Journal Article Cacheris, A. ; Abrams, T. ; Baylor, L. R. ; ... - Plasma Physics and Controlled Fusion

Abstract Edge localized modes (ELMs) in H-mode plasmas erode plasma-facing components (PFCs) and lead to impurities in the core, reducing confinement. This study analyzes D2 pellet injection on the DIII-D fusion experiment used as an ELM mitigation technique applied during the 2016 tungsten Metal Rings Campaign to reduce W erosion during ELMs. The 400.9 nm photon wavelength line emission intensity of tungsten atoms (WI) filterscope channels and Langmuir probes were used to infer the gross erosion rate of tungsten-coated tiles installed in the divertor of DIII-D. D2 mass injection rates ranging from 34 to 41 arbitrary units (A.U.) and nomore »« less
https://doi.org/10.1088/1361-6587/acd026
Divertor erosion in DIII-D

Technical Report Whyte, D G ; Bastasz, R ; Wampler, W R ; ...

Net erosion rates of carbon target plates have been measured in situ for the DIII-D lower divertor. The principal method of obtaining this data is the DiMES sample probe. Recent experiments have focused on erosion at the outer strike-point of two divertor plasma conditions: (1) attached (Te > 40 eV) ELMing plasmas and (2) detached (Te < 2 eV) ELMing plasmas. The erosion rates for the attached cases are > 10 cm/year, even with incident heat flux < 1 MW/m{sup 2}. In this case, measurements and modeling agree for both gross and net carbon erosion, showing the near-surface transport andmore »« less
https://doi.org/10.2172/654183

Full Text Available
Modeling of ExB effects on tungsten re-deposition and transport in the DIII-D divertor

Journal Article Nichols, J. H. ; Abrams, T. ; Chrobak, C. P. ; ... - Nuclear Fusion

Mixed-material DIVIMP-WallDYN modelling, now incorporating ExB drifts, is presented that simultaneously reproduces tungsten (W) erosion and deposition patterns observed during the DIII-D Metal Rings Campaign, in which a toroidally symmetric set of W-coated tiles were installed in the carbon (C) DIII-D divertor. Since most reactor plasma facing component (PFC) designs call for mixed-material environments, including ITER’s W/Be enviroment, the divertor targets will quickly evolve into reconstitued surfaces of multiple elements. This work identifies controlling physics that affects material migration patterns in the divertor, which impact PFC lifetimes and impurity leakage from the divertor to the core. These simulations indicate thatmore »« less
https://doi.org/10.1088/1741-4326/ac14e6

Full Text Available

Similar Records