Overview of R&D on Plasma-Facing Materials and Components in China-Reference-Cited by-同舟云学术

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Overview of R&D on Plasma-Facing Materials and Components in China

Published:2012-08 Issue:1 Volume:62 Page:9-15
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Luo G.-N.¹,Li Q.¹,Chen J. M.²,Liu X.²,Liu W.³,Zhou Z. J.⁴,Yao D. M.¹

Affiliation:

1. Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP), Hefei, Anhui, China

2. Southwest Institute of Physics (SWIP), Chengdu, Sichuan, China

3. Tsinghua University (THU), Beijing, China

4. University of Science and Technology Beijing (USTB), Beijing, China

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/10.13182/FST12-A14104

Reference13 articles.

1. Overview of plasma-facing materials and components for EAST

2. Fabrication and characterization of ultra-fine grained tungsten by resistance sintering under ultra-high pressure

3. Coating materials for fusion application in China

4. Pre-brazed casting and hot radial pressing: A reliable process for the manufacturing of CFC and W monoblock mock-ups

5. Testing of high heat flux components manufactured by ENEA for ITER divertor

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1. Effect of nanosecond laser irradiation on tungsten grain structure;Nuclear Materials and Energy;2024-09

2. Melting of W/Cu flat type component for main limiter and its impact on plasma operation in EAST experiments;Nuclear Fusion;2024-06-28

3. Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments;Nuclear Fusion;2024-06-03

4. Interface cracking damage of W/Cu monoblocks as divertor target after high-cyclic plasma discharges in EAST;Nuclear Materials and Energy;2024-06

5. Failure analysis of damaged tungsten monoblock components of upper divertor outer target in EAST fusion device;Nuclear Engineering and Technology;2024-06

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