Thermal management of tungsten leading edges in DIII-D

R. E. Nygren; D. L. Rudakov; C. Murphy; J. D. Watkins; E. A. Unterberg; J. L. Barton; P. C. Stangeby

doi:10.1016/j.fusengdes.2017.04.060

Thermal management of tungsten leading edges in DIII-D

R. E. Nygren
, D. L. Rudakov
, C. Murphy
, J. D. Watkins
, E. A. Unterberg
, J. L. Barton
, P. C. Stangeby

Fusion Engineering

Research output: Contribution to journal › Article › peer-review

6 Scopus citations

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 >3000 °C in a 3-s shot with a (parallel) heat load of ∼80 MW/m² and ∼8.6 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 arrays of divertor tiles had W-coated molybdenum inserts 50 mm wide radially. This paper presents data and thermal analyses.

Original language	English
Pages (from-to)	271-275
Number of pages	5
Journal	Fusion Engineering and Design
Volume	124
DOIs	https://doi.org/10.1016/j.fusengdes.2017.04.060
State	Published - Nov 2017

Keywords

DIII-D
High heat flux
Plasma facing component
Plasma surface interaction
Power handling
Tungsten

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10.1016/j.fusengdes.2017.04.060

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

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 >3000 °C in a 3-s shot with a (parallel) heat load of ∼80 MW/m2 and ∼8.6 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 arrays of divertor tiles had W-coated molybdenum inserts 50 mm wide radially. This paper presents data and thermal analyses.",

keywords = "DIII-D, High heat flux, Plasma facing component, Plasma surface interaction, Power handling, Tungsten",

author = "Nygren, \{R. E.\} and Rudakov, \{D. L.\} and C. Murphy and Watkins, \{J. D.\} and Unterberg, \{E. A.\} and Barton, \{J. L.\} and Stangeby, \{P. C.\}",

note = "Publisher Copyright: {\textcopyright} 2017",

year = "2017",

month = nov,

doi = "10.1016/j.fusengdes.2017.04.060",

language = "English",

volume = "124",

pages = "271--275",

journal = "Fusion Engineering and Design",

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TY - JOUR

T1 - Thermal management of tungsten leading edges in DIII-D

AU - Nygren, R. E.

AU - Rudakov, D. L.

AU - Murphy, C.

AU - Watkins, J. D.

AU - Unterberg, E. A.

AU - Barton, J. L.

AU - Stangeby, P. C.

PY - 2017/11

Y1 - 2017/11

N2 - 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 >3000 °C in a 3-s shot with a (parallel) heat load of ∼80 MW/m2 and ∼8.6 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 arrays of divertor tiles had W-coated molybdenum inserts 50 mm wide radially. This paper presents data and thermal analyses.

AB - 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 >3000 °C in a 3-s shot with a (parallel) heat load of ∼80 MW/m2 and ∼8.6 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 arrays of divertor tiles had W-coated molybdenum inserts 50 mm wide radially. This paper presents data and thermal analyses.

KW - DIII-D

KW - High heat flux

KW - Plasma facing component

KW - Plasma surface interaction

KW - Power handling

KW - Tungsten

UR - https://www.scopus.com/pages/publications/85018334167

U2 - 10.1016/j.fusengdes.2017.04.060

DO - 10.1016/j.fusengdes.2017.04.060

M3 - Article

AN - SCOPUS:85018334167

SN - 0920-3796

VL - 124

SP - 271

EP - 275

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

ER -

Thermal management of tungsten leading edges in DIII-D

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Keywords

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