Effect of Y2O3 particles on the helium ion irradiation damage of W-2%Y2O3 composite prepared by wet chemical method-Reference-Cited by-同舟云学术

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Effect of Y2O3 particles on the helium ion irradiation damage of W-2%Y2O3 composite prepared by wet chemical method

Published:2019-06 Issue: Volume:6 Page:100268
ISSN:2589-1529
Container-title:Materialia
language:en
Short-container-title:Materialia

Author:

Yao Gang,Luo Lai-Ma,Tan Xiao-Yue,Zan Xiang^ORCID,Xu Qiu,Zhu Xiao-Yong,Lu Er-Yang,Cao Xing-Zhong^ORCID,Cheng Ji-Gui,Wu Yu-Cheng

Funder

the National Key

Research and Development

National Natural Science Foundation of China

The Fundamental Research Funds for the Central Universities

The Foundation of Laboratory of Nonferrous Metal Material and Processing Engineering of Anhui Province

111 Project

Publisher

Elsevier BV

Subject

General Materials Science

Reference26 articles.

1. DEMO divertor limitations during and in between ELMs;Wenninger;Nucl. Fus.,2014

2. Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials;Wurster;J. Nucl. Mater.,2013

3. Development of advanced high heat flux and plasma-facing materials;Linsmeier;Nucl. Fus.,2017

4. Surface modifications of W divertor components for EAST during exposure to high heat loads with He;Li;J. Nucl. Mater.,2015

5. Mutation of vacancies to divacancies by helium trapping in molybdenum effect on the onset of percolation;Caspers;Phys. Status Solidi,2010

Cited by 20 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. Synthesis and characterization of W-Y2O3 composites with core-shell structure via wet chemical method in an acidic solution;International Journal of Refractory Metals and Hard Materials;2024-08

2. Surface modification of ZrC dispersion-strengthened W under low energy He plasma irradiation;Nuclear Fusion;2024-03-15

3. Evolution of irradiation damage in tungsten matrix and Y2O3 phase after low energy helium plasma exposure;Journal of Nuclear Materials;2024-02

4. Composite effect of helium ion irradiation and transient thermal shock on recrystallized pure W and W-Y2O3 alloys;Fusion Engineering and Design;2023-11

5. Interfacial microstructure and thermal shock resistance of diffusion bonding ODS-W and molybdenum alloy by spark plasma sintering;International Journal of Refractory Metals and Hard Materials;2022-09

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