Dislocation loops and hardening of silicon ion irradiated W and W-3Re alloy at 400 °C and 550 °C-Reference-Cited by-同舟云学术

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Dislocation loops and hardening of silicon ion irradiated W and W-3Re alloy at 400 °C and 550 °C

Published:2024-09 Issue: Volume:598 Page:155192
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Luo Fengfeng,Luo Hongtai,Liu Qiuxiang,Chen Liheng,Lin Wenbin,Long Yunxiang,Guo Liping^ORCID

Publisher

Elsevier BV

Reference44 articles.

1. Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components;Barrett;Fusion Eng. Des.,2016

2. European divertor target concepts for DEMO: design rationales and high heat flux performance;You;Nucl. Mater. Energy.,2018

3. An overview of oxidation-resistant tungsten alloys for nuclear fusion;Liu;J. Alloys Compd.,2018

4. Microstructure and performances of W–TiC–Y2O3 composites prepared by mechano-chemical and wet-chemical methods;Lin;J. Alloys Compd.,2018

5. Physics basis and design of the ITER plasma-facing components;Pitts;J. Nucl. Mater.,2011

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