High Heat Flux Testing of Castellated Graphite Plasma- Facing Components-Reference-Cited by-同舟云学术

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High Heat Flux Testing of Castellated Graphite Plasma- Facing Components

Published:2020-11-03 Issue:1 Volume:77 Page:9-18
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Gray T. K.¹,Youchison D. L.¹,Ellis R. E.²,Jaworski M. A.²,Khodak A.²,Looby T.³,Reinke M. L.¹,Smalley G.²,Wolfe D. E.⁴

Affiliation:

1. Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831

2. Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543-0451

3. University of Tennessee–Knoxville, Knoxville, Tennessee

4. Pennsylvania State University, Applied Research Laboratory, State College, Pennsylvania

Publisher

Informa UK Limited

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/15361055.2020.1831872

Reference13 articles.

1. Exploration of spherical torus physics in the NSTX device

2. Overview of the physics and engineering design of NSTX upgrade

3. Physics basis for the first ITER tungsten divertor

4. Plasma wall interaction and its implication in an all tungsten divertor tokamak

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Divertor heat load estimates on NSTX and DIII-D using new and open-source 2D inversion analysis code;Nuclear Fusion;2024-07-23

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