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Chinese Academy of Sciences Institutional Repositories Grid
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CAS IR Grid
机构
合肥物质科学研究院 [21]
采集方式
OAI收割 [21]
内容类型
期刊论文 [21]
发表日期
2024 [4]
2023 [1]
2022 [5]
2021 [5]
2020 [2]
2018 [1]
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Modelling study of divertor W leakage for different divertor conditions with Ne seeding in EAST tokamak
期刊论文
OAI收割
NUCLEAR FUSION, 2024, 卷号: 64
作者:
Xu, Guoliang
;
Wang, Hui
;
Ding, Rui
;
Si, Hang
;
Jia, Guozhang
  |  
收藏
  |  
浏览/下载:13/0
  |  
提交时间:2024/11/20
divertor
tungsten
impurity transport
E x B drifts
EAST
Improving interfacial microstructure and mechanical properties of ODS-W/ Cu joints via anodization treatment and spark plasma sintering
期刊论文
OAI收割
JOURNAL OF NUCLEAR MATERIALS, 2024, 卷号: 601
作者:
Xu, Dang
;
Fu, Kaichao
;
Sang, Changcheng
;
Chen, Ruizhi
;
Chen, Pengqi
  |  
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2024/11/20
ODS-W/Cu joints
Anodization treatment
SPS bonding technology
Interfacial microstructure
Mechanical properties
Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments
期刊论文
OAI收割
NUCLEAR FUSION, 2024, 卷号: 64
作者:
Guo, Zongxiao
;
Zhu, Dahuan
;
Yan, Rong
;
Xuan, Chuannan
;
Wang, Baoguo
  |  
收藏
  |  
浏览/下载:4/0
  |  
提交时间:2024/11/20
W/Cu monoblocks
damages
transient heat flux
heat exhaust capacity
EAST
ITER
Failure analysis of damaged tungsten monoblock components of upper divertor outer target in EAST fusion device
期刊论文
OAI收割
NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 卷号: 56
作者:
Wang, Kang
;
Xi, Ya
;
Zan, Xiang
;
Zhu, Dahuan
;
Luo, Laima
  |  
收藏
  |  
浏览/下载:7/0
  |  
提交时间:2024/11/20
Tungsten monoblock
Crack
Recrystallization
Divertor
EAST fusion device
Deuterium erosion and retention properties on MoAlB ceramics by ion irradiation
期刊论文
OAI收割
VACUUM, 2023, 卷号: 207
作者:
Li, Cong
;
Tu, Hanjun
;
Zhang, Dongya
;
Zhu, Dahuan
;
Shi, Liqun
  |  
收藏
  |  
浏览/下载:48/0
  |  
提交时间:2022/12/23
Deuterium concentration
Sputtering yield
Erosion
TRIDYN
Modelling of tungsten impurity edge transport and screening for different divertor conditions in EAST
期刊论文
OAI收割
NUCLEAR FUSION, 2022, 卷号: 62
作者:
Wang, Hui
;
Xu, Guoliang
;
Ding, Rui
;
Liu, Xiaoju
;
Si, Hang
  |  
收藏
  |  
浏览/下载:57/0
  |  
提交时间:2022/12/22
divertor
tungsten erosion
impurity transport
EAST
DIVIMP
Comparative modeling studies of carbon and tungsten impurity transport in the boundary plasma of EAST with a partially detached divertor condition
期刊论文
OAI收割
NUCLEAR MATERIALS AND ENERGY, 2022, 卷号: 33
作者:
Xu, Guoliang
;
Wang, Hui
;
Ding, Rui
;
Liu, Xiaoju
;
Si, Hang
  |  
收藏
  |  
浏览/下载:54/0
  |  
提交时间:2022/12/22
Characterization of dust produced during the 2021 first campaign in EAST tokamak
期刊论文
OAI收割
NUCLEAR MATERIALS AND ENERGY, 2022, 卷号: 33
作者:
Pan, Hongyan
;
Ding, Rui
;
Peng, Jiao
;
Yan, Rong
;
Zhu, Dahuan
  |  
收藏
  |  
浏览/下载:37/0
  |  
提交时间:2022/12/22
Dust
Material analysis
Lithium
EAST
Numerical analysis of recrystallization behaviors for W monoblock under cyclic high heat flux
期刊论文
OAI收割
NUCLEAR MATERIALS AND ENERGY, 2022, 卷号: 32
作者:
Li, Changjun
;
Zhu, Dahuan
;
Ding, Rui
;
Guo, Zongxiao
;
Xuan, Chuannan
  |  
收藏
  |  
浏览/下载:47/0
  |  
提交时间:2022/12/22
Recrystallization
Monoblock
High heat flux
Plasma facing component
Numerical analysis
Studies of material migration and deposition after the 2017 experimental campaign in EAST
期刊论文
OAI收割
NUCLEAR MATERIALS AND ENERGY, 2022, 卷号: 30
作者:
Yan, Rong
;
Peng, Jiao
;
Li, Changjun
;
Xu, Guoliang
;
Ding, Rui
  |  
收藏
  |  
浏览/下载:92/0
  |  
提交时间:2022/01/25
Tokamak
Plasma-facing material
Deposition
Migration