Evolution of Dislocation Loops in 30 keV He<sup>+</sup>-Irradiated W–0.5% ZrC Alloys: In Situ TEM Observations and Molecular Dynamics Simulations-Reference-Cited by-同舟云学术

Evolution of Dislocation Loops in 30 keV He⁺-Irradiated W–0.5% ZrC Alloys: In Situ TEM Observations and Molecular Dynamics Simulations

Published:2022-02-02 Issue:2 Volume:5 Page:2442-2451
ISSN:2574-0962
Container-title:ACS Applied Energy Materials
language:en
Short-container-title:ACS Appl. Energy Mater.

Author:

Liu Xinyi¹²,Chen Zhe³,Wang Hao³,Li Yipeng¹²,Xie Zhuoming⁴,Liu Xiang³,Ran Guang¹²^ORCID

Affiliation:

1. College of Energy, Xiamen University, Xiamen 361102, China

2. Fujian Research Center for Nuclear Engineering, Xiamen 361102, China

3. Southwestern Institute of Physics, Chengdu 610041, China

4. Key Laboratory of Materials Physics, Institute of Solid State Physics, Chinese Academy of Sciences, Hefei 230031, China

Funder

National Natural Science Foundation of China

Publisher

American Chemical Society (ACS)

Subject

Electrical and Electronic Engineering,Materials Chemistry,Electrochemistry,Energy Engineering and Power Technology,Chemical Engineering (miscellaneous)

Link

https://pubs.acs.org/doi/pdf/10.1021/acsaem.1c03915

Reference48 articles.

1. Development of ultra-fine grained W–TiC and their mechanical properties for fusion applications

2. Microstructure and Mechanical Properties of Nano-Size Zirconium Carbide Dispersion Strengthened Tungsten Alloys Fabricated by Spark Plasma Sintering Method

3. Recrystallization and thermal shock fatigue resistance of nanoscale ZrC dispersion strengthened W alloys as plasma-facing components in fusion devices

4. Recent progress on the R&D of W-ZrC alloys for plasma facing components in fusion devices

5. Impact of neutron irradiation on hardening of baseline and advanced tungsten grades and its link to initial microstructure

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