Thermal management of tungsten leading edges in DIII-D

Nygren, Richard E.; Rudakov, Dmitry L.; Murphy, Christopher; Watkins, Jonathan D.; Unterberg, Ezekial A.; Barton, Joseph L.; Stangeby, Peter C.

doi:10.1016/j.fusengdes.2017.04.060

Title: Thermal management of tungsten leading edges in DIII-D

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Abstract

The DiMES materials probe exposed tungsten blocks with 0.3 and 1 mm high leading edges to DIII-D He plasmas in 2015 and 2016 viewed with high resolution IRTV. The 1-mm edge may have reached >2400° C in a 3-s shot with a (parallel) heat load of ~50 MW/m² and ~10 MW/m² on the surface based on modeling. The experiments support ITER. Leading edges were also a concern in the DIII-D Metal Tile Experiment in 2016. Two toroidal rings of divertor tiles had W-coated molybdenum inserts 50 mm wide radially. This study presents data and thermal analyses.

Authors:

Nygren, Richard E. ^[1]; Rudakov, Dmitry L. ^[2]; Murphy, Christopher ^[3]; Watkins, Jonathan D. ^[1]; Unterberg, Ezekial A. ^[4]; Barton, Joseph L. ^[1]; Stangeby, Peter C. ^[5]

Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Univ. of California, San Diego, La Jolla, CA (United States)
General Atomics, San Diego, CA (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Toronto Institute for Aerospace Studies, Toronto (Canada)

Publication Date:: Sat Apr 29 00:00:00 EDT 2017

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

Sponsoring Org.:: USDOE

OSTI Identifier:: 1373578

Grant/Contract Number:: FC02-04ER54698

Resource Type:: Accepted Manuscript

Journal Name:: Fusion Engineering and Design

Additional Journal Information:: Journal Volume: 124; Journal ID: ISSN 0920-3796

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Plasma facing component; Tungsten; High heat flux; DIII-D; Power handling; Plasma surface interaction

Citation Formats


                    Nygren, Richard E., Rudakov, Dmitry L., Murphy, Christopher, Watkins, Jonathan D., Unterberg, Ezekial A., Barton, Joseph L., and Stangeby, Peter C. Thermal management of tungsten leading edges in DIII-D.  United States: N. p., 2017. 
Web.  doi:10.1016/j.fusengdes.2017.04.060.

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                    Nygren, Richard E., Rudakov, Dmitry L., Murphy, Christopher, Watkins, Jonathan D., Unterberg, Ezekial A., Barton, Joseph L., & Stangeby, Peter C. Thermal management of tungsten leading edges in DIII-D.  United States.  https://doi.org/10.1016/j.fusengdes.2017.04.060

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                    Nygren, Richard E., Rudakov, Dmitry L., Murphy, Christopher, Watkins, Jonathan D., Unterberg, Ezekial A., Barton, Joseph L., and Stangeby, Peter C. Sat .  
"Thermal management of tungsten leading edges in DIII-D".  United States.  https://doi.org/10.1016/j.fusengdes.2017.04.060.  https://www.osti.gov/servlets/purl/1373578.

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@article{osti_1373578,

  title        = {Thermal management of tungsten leading edges in DIII-D},

  author       = {Nygren, Richard E. and Rudakov, Dmitry L. and Murphy, Christopher and Watkins, Jonathan D. and Unterberg, Ezekial A. and Barton, Joseph L. and Stangeby, Peter C.},

  abstractNote = {The DiMES materials probe exposed tungsten blocks with 0.3 and 1 mm high leading edges to DIII-D He plasmas in 2015 and 2016 viewed with high resolution IRTV. The 1-mm edge may have reached >2400° C in a 3-s shot with a (parallel) heat load of ~50 MW/m2 and ~10 MW/m2 on the surface based on modeling. The experiments support ITER. Leading edges were also a concern in the DIII-D Metal Tile Experiment in 2016. Two toroidal rings of divertor tiles had W-coated molybdenum inserts 50 mm wide radially. This study presents data and thermal analyses.},

  doi          = {10.1016/j.fusengdes.2017.04.060},

  journal      = {Fusion Engineering and Design},

  number       = ,

  volume       = 124,

  place        = {United States},

  year         = {Sat Apr 29 00:00:00 EDT 2017},

  month        = {Sat Apr 29 00:00:00 EDT 2017}

}

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