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合肥物质科学研究院 [5]
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Microstructural damage evolution of (WTiVNbTa)C-5 high-entropy carbide ceramics induced by self-ions irradiation
期刊论文
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY, 2022, 卷号: 42, 期号: 6, 页码: 2567-2576
作者:
Zhu, Yabin
;
Chai, Jianlong
;
Wang, Zhiguang
;
Shen, Tielong
;
Niu, Lijuan
收藏
  |  
浏览/下载:27/0
  |  
提交时间:2022/04/11
High-entropy ceramic
Ion irradiation
Damage evolution
Mechanical properties
Performance of W-1%Y2O3-0.5%Ti Plasma-Facing Composite Under Fusion Relevant Transient Heat Flux
期刊论文
FUSION SCIENCE AND TECHNOLOGY, 2021
作者:
Li, Changjun
;
Zhu, Dahuan
;
Li, Xiangbin
;
Chen, Junling
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  |  
浏览/下载:37/0
  |  
提交时间:2021/05/17
W-1%Y2O3-0.5%Ti
plasma-facing composite
transient heat flux
EMS-60
damage
Irradiation response of Al2O3-ZrO2 ceramic composite under He ion irradiation
期刊论文
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY, 2021, 卷号: 41, 期号: 4, 页码: 2883-2891
作者:
Liu, Yiwen
;
Zhu, Yabin
;
Shen, Tielong
;
Chai, Jianlong
;
Niu, Lijuan
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  |  
浏览/下载:42/0
  |  
提交时间:2021/12/10
He ion
Irradiation damage
Mechanical properties
Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation
期刊论文
NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 卷号: 52
作者:
Ding, Xiao-Yu
;
Xu, Qiu
;
Zhu, Xiao-yong
;
Luo, Lai-Ma
;
Huang, Jian-Jun
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  |  
浏览/下载:135/0
  |  
提交时间:2020/12/07
Oxide dispersion-strengthened
Pre-irradiation
Microstructure evolution
He+ ions
Deuterium retention
Assessing fracture toughness in sintered Al2O3-ZrO2(3Y)-SiC ceramic composites through indentation technique
期刊论文
CERAMICS INTERNATIONAL, 2020, 卷号: 46, 期号: 17, 页码: 27143-27149
作者:
Chai, Jianlong
;
Zhu, Yabin
;
Shen, Tielong
;
Liu, Yiwen
;
Niu, Lijuan
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  |  
浏览/下载:56/0
  |  
提交时间:2021/12/15
Al2O3-ZrO2(3Y)-SiC
Indentation technique
Toughness fracture
Toughening mechanism
Initial investigation of B4C-TiB2 composites as neutron absorption material for nuclear reactors
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 539, 页码: 9
作者:
Wang, Ji
;
Ren, Donglou
;
Chen, LeiLei
;
Man, Guian
;
Zhang, Houyuan
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  |  
浏览/下载:41/0
  |  
提交时间:2021/12/15
Neutron absorber
B4C pellet
He irradiation
Crack propagation
Finite element
Mechanical and thermal properties of light weight boron-mullite Al5BO9
期刊论文
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 2020, 页码: 13
作者:
Ren, Yixiao
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  |  
浏览/下载:35/0
  |  
提交时间:2021/02/02
Al5BO9
boron-mullite
lightweight ceramics
mechanical properties
thermal properties
Mechanical and thermal properties of light weight boron-mullite Al5BO9
期刊论文
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 2020, 卷号: 103, 期号: 10, 页码: 13
作者:
Ren, Yixiao
;
Dai, Fu-Zhi
;
Xiang, Huimin
;
Wang, Xiaohui
;
Sun, Luchao
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  |  
浏览/下载:47/0
  |  
提交时间:2021/02/02
Al5BO9
boron-mullite
lightweight ceramics
mechanical properties
thermal properties
Irradiation hardening behaviors of tungsten-potassium alloy studied by accelerated 3-MeVW2+ ions*
期刊论文
CHINESE PHYSICS B, 2020, 卷号: 29
作者:
Yang, Xiao-Liang
;
Chen, Long-Qing
;
Qiu, Wen-Bin
;
Song, Yang-Yi-Peng
;
Tang, Yi
收藏
  |  
浏览/下载:17/0
  |  
提交时间:2020/11/26
irradiation harden
spark plasma sintering
WK alloy
nanoindentation
Initial investigation of B4C-TiB2 composites as neutron absorption material for nuclear reactors
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 539
作者:
Wang, Ji
;
Ren, Donglou
;
Chen, LeiLei
;
Man, Guian
;
Zhang, Houyuan
收藏
  |  
浏览/下载:14/0
  |  
提交时间:2020/12/16
BORON-CARBIDE
CRACK-PROPAGATION
HELIUM
DAMAGE
MICROSTRUCTURE
IRRADIATION
STRENGTH
BEHAVIOR
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