Thermal management of tungsten leading edges in DIII-D

被引：6
|
作者：
Nygren, R. E. [1 ]
Rudakov, D. L. [2 ]
Murphy, C. [3 ]
Watkins, J. D. [1 ]
Unterberg, E. A. [4 ]
Barton, J. L. [1 ]
Stangeby, P. C. [5 ]
机构：
[1] Sandia Natl Labs, POB 5800, Albuquerque, NM 87185 USA
[2] Univ Calif San Diego, La Jolla, CA 92093 USA
[3] Gen Atom Co, POB 85608, San Diego, CA 92186 USA
[4] Oak Ridge Natl Lab, Oak Ridge, TN 37830 USA
[5] Univ Toronto, Inst Aerosp Studies, Toronto, ON M3H 5T6, Canada
来源：
FUSION ENGINEERING AND DESIGN | 2017年 / 124卷
关键词：
Plasma facing component; Tungsten; High heat flux; DIII-D; Power handling; Plasma surface interaction;
D O I：
10.1016/j.fusengdes.2017.04.060
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
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 degrees C in a 3-s shot with a (parallel) heat load of similar to 80 MW/m(2) and similar to 8.6 MW/m(2) 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 50mm wide radially. This paper presents data and thermal analyses. (C) 2017 Published by Elsevier B.V.
引用
收藏
页码：271 / 275
页数：5
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