中国科学院机构知识库网格
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 [31]
近代物理研究所 [1]
采集方式
OAI收割 [32]
内容类型
期刊论文 [32]
发表日期
2024 [1]
2022 [2]
2021 [6]
2020 [8]
2019 [1]
2018 [8]
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Design and Strength Analysis of the Lifting Process for CFETR TF Coil Manufacturing
期刊论文
OAI收割
IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2024, 卷号: 34
作者:
Tong, Yunhua
;
Gao, Xiang
;
Cao, Lei
;
Du, Shijun
;
Wu, Yu
  |  
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2024/11/22
China Fusion Engineering Test Reactor (CFETR) toroidal field (TF) coil
design
lifting process
strength analysis
Decomposition and estimation of the pulsed active power of the CPSS in the CFETR tokamak reactor based on the FFT and improved Prony methods
期刊论文
OAI收割
ENERGY REPORTS, 2022, 卷号: 8
作者:
Hua, Yuting
;
Fu, Peng
;
Huang, Liansheng
;
Li, Shenghu
  |  
收藏
  |  
浏览/下载:74/0
  |  
提交时间:2022/01/25
Active power decomposition
Chinese Fusion Engineering Test Reactor (CFETR)
Coil power supply system (CPSS)
Exceeding of parameters
Fast Fourier Transform (FFT)
Prony method
Systematic design of snake arm maintainer in nuclear industry
期刊论文
OAI收割
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 176
作者:
Qin, Guodong
;
Cheng, Yong
;
Pan, Hongtao
;
Zhao, Wenlong
;
Shi, Shanshuang
  |  
收藏
  |  
浏览/下载:63/0
  |  
提交时间:2022/05/16
Chinese fusion engineering test reactor
Snake arm maintainer
Layered drive
Multi-purpose overload robot
Design of Coordination System for Composite Mobile Robot Platform Oriented to Nuclear Fusion Vessel
期刊论文
OAI收割
JOURNAL OF FUSION ENERGY, 2021, 卷号: 40
作者:
Zhang, Qiang
;
Song, Bo
  |  
收藏
  |  
浏览/下载:90/0
  |  
提交时间:2021/11/15
EAST nuclear fusion reactor vessel
Multi-joint remote control system
Composite multi-joint remote operation robot platform
Bidirectional coordinated control
Load-bearing performance test
Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2021, 卷号: 49
作者:
Li, Jie
;
Zhang, Jie
;
Liu, Changle
;
Liu, Xiaogang
;
Gao, Xiang
  |  
收藏
  |  
浏览/下载:72/0
  |  
提交时间:2021/11/15
Neutrons
Plasmas
Solid modeling
Inductors
Production
Optimization
Loading
China Fusion Engineering Test Reactor (CFETR)
neutronics study
neutron wall loading (NWL)
tritium breeding ratio (TBR)
water-cooled ceramic breeder (WCCB)
Scoping study of lower hybrid current drive for CFETR
期刊论文
OAI收割
NUCLEAR FUSION, 2021, 卷号: 61
作者:
Wallace, G. M.
;
Din, B. J.
;
Li, M. H.
;
Chen, J.
;
Baek, S. G.
  |  
收藏
  |  
浏览/下载:41/0
  |  
提交时间:2021/11/01
lower hybrid current drive
china fusion engineering test reactor
non-inductive current drive
steady state tokamak
Quench Analysis of the CFETR TF Coil Using the Gandalf Code
期刊论文
OAI收割
IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2021, 卷号: 31
作者:
Wen, Xinghao
;
Li, Junjun
;
Sang, Aiguo
;
Ren, Yong
;
Liu, Xiaogang
  |  
收藏
  |  
浏览/下载:36/0
  |  
提交时间:2021/04/26
China fusion engineering test reactor (CFETR)
quench
superconducting magnet
thermal-hydraulic
Edge localized mode characteristics and divertor heat flux during stationary and transient phase for CFETR hybrid scenario
期刊论文
OAI收割
PLASMA PHYSICS AND CONTROLLED FUSION, 2021, 卷号: 63
作者:
Li, Zeyu
;
Zhu, Yiren
;
Xu, Guoliang
;
Chan, V. S.
;
Xu, Xueqiao
  |  
收藏
  |  
浏览/下载:37/0
  |  
提交时间:2021/03/15
China Fusion Engineering Test Reactor
grassy edge localized mode
transient heat flux
heat flux width
melting
tungsten erosion
Numerical simulation of very high harmonic fast waves for an off-axis current drive in a China fusion engineering test reactor by the GENRAY code
期刊论文
OAI收割
PLASMA PHYSICS AND CONTROLLED FUSION, 2021, 卷号: 63
作者:
Yang, Y. Q.
;
Zhang, X. J.
;
Zhao, Y. P.
;
Qin, C. M.
  |  
收藏
  |  
浏览/下载:26/0
  |  
提交时间:2021/03/15
China fusion engineering test reactor
current drive
helicon wave
The Mechanical Analyses of CFETR CSMC Local Components Under the Steady-Operating Condition
期刊论文
OAI收割
IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2020, 卷号: 30
作者:
Wang, Xianwei
;
Xu, Aihua
;
Wang, Zhaoliang
  |  
收藏
  |  
浏览/下载:68/0
  |  
提交时间:2020/10/26
Central solenoid model coil (CSMC)
China fusion engineering test reactor (CFETR)
current lead joint
electromagnetic force
joggle