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科研机构
合肥物质科学研究院 [16]
内容类型
期刊论文 [16]
发表日期
2022 [16]
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Improvement of lower hybrid current drive systems for high-power and long-pulse operation on EAST
期刊论文
NUCLEAR ENGINEERING AND TECHNOLOGY, 2022, 卷号: 54
作者:
Wang, M.
;
Liu, L.
;
Zhao, L. M.
;
Li, M. H.
;
Ma, W. D.
收藏
  |  
浏览/下载:20/0
  |  
提交时间:2022/12/23
Lower hybrid current drive
Hot spots
Fast electrons
Long -pulse operation
Tokamak
A new method to reduce the toroidal field ripple effect due to the ferromagnetic materials in updated CFETR
期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 184
作者:
Liu, Zhao
;
Wang, Ming
;
Lei, Mingzhun
;
Gu, Yi
收藏
  |  
浏览/下载:13/0
  |  
提交时间:2022/12/22
CFETR
WCCB blanket
Diagnostic system
Toroidal field ripple
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
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:21/0
  |  
提交时间:2022/12/22
Spatiotemporal dynamic characterization of the laser-induced plasma of a mixed material (WCCu) under variable ablation angles in a vacuum
期刊论文
JOURNAL OF ANALYTICAL ATOMIC SPECTROMETRY, 2022
作者:
Wu, Huace
;
Li, Cong
;
Wu, Ding
;
Liu, Shiming
;
Hu, Zhenhua
收藏
  |  
浏览/下载:18/0
  |  
提交时间:2022/12/22
Numerical analysis of recrystallization behaviors for W monoblock under cyclic high heat flux
期刊论文
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:21/0
  |  
提交时间:2022/12/22
Recrystallization
Monoblock
High heat flux
Plasma facing component
Numerical analysis
Microstructure and mechanical properties of in-situ formed ZrC nanoparticles dispersion-strengthened tungsten alloy
期刊论文
INTERNATIONAL JOURNAL OF REFRACTORY METALS & HARD MATERIALS, 2022, 卷号: 107
作者:
Cheng, X.
;
Jing, K.
;
Xie, Z. M.
;
Liu, R.
;
Wu, X. B.
收藏
  |  
浏览/下载:13/0
  |  
提交时间:2022/12/23
Tungsten
Dispersion strengthening
Microstructure
Dissolution-precipitation
Mechanical properties
Fabrication and performance examination on explosively welded ODS-Cu / 316 L clad plate for CFETR divertor heat sink
期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 180
作者:
Mou, Nanyu
;
Zhuang, Qing
;
Zhang, Xiyang
;
Han, Le
;
Jiang, Beiyan
收藏
  |  
浏览/下载:14/0
  |  
提交时间:2022/12/23
Explosive welding
ODS-Cu
316 l stainless steel
Bonding quality
CFETR
Optimization of a WCCB blanket module with detached first wall for CFETR
期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 179
作者:
Ma, Xuebin
;
Yu, Yi
;
Wu, Qiuran
;
Jiang, Kecheng
;
Liu, Songlin
收藏
  |  
浏览/下载:8/0
  |  
提交时间:2022/12/23
CFETR
Detached first wall
WCCB blanket
Optimization
Corrosion characteristics of Mo and TZM alloy for plasma facing components in molten lithium at 623 K
期刊论文
CORROSION SCIENCE, 2022, 卷号: 200
作者:
Meng, X. C.
;
Li, L.
;
Li, C. L.
;
Andruczyk, D.
;
Tritz, K.
收藏
  |  
浏览/下载:30/0
  |  
提交时间:2022/05/16
Corrosion
Liquid lithium
Mo-based alloy
PFM
Blanket components
Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation
期刊论文
NUCLEAR FUSION, 2022, 卷号: 62
作者:
Bucalossi, J.
;
Achard, J.
;
Agullo, O.
;
Alarcon, T.
;
Allegretti, L.
收藏
  |  
浏览/下载:119/0
  |  
提交时间:2022/03/21
nuclear fusion
magnetic confinement
tokamak physics
divertor
WEST
ITER
DEMO
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