×
验证码:
换一张
忘记密码?
记住我
CORC
首页
科研机构
检索
知识图谱
申请加入
托管服务
登录
注册
在结果中检索
科研机构
合肥物质科学研究院 [34]
清华大学 [22]
西安交通大学 [3]
上海应用物理研究所 [2]
力学研究所 [1]
北京大学 [1]
更多...
内容类型
期刊论文 [68]
会议论文 [3]
发表日期
2022 [3]
2021 [6]
2020 [9]
2019 [3]
2018 [11]
2017 [5]
更多...
×
知识图谱
CORC
开始提交
已提交作品
待认领作品
已认领作品
未提交全文
收藏管理
QQ客服
官方微博
反馈留言
浏览/检索结果:
共71条,第1-10条
帮助
已选(
0
)
清除
条数/页:
5
10
15
20
25
30
35
40
45
50
55
60
65
70
75
80
85
90
95
100
排序方式:
请选择
作者升序
作者降序
题名升序
题名降序
发表日期升序
发表日期降序
提交时间升序
提交时间降序
Design of DC Magnet Power Supply System for ITER Static Magnetic Field Test Facility
期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2022
作者:
Deng, Xi
;
Jiang, Li
;
Huang, Ya
;
Gao, Ge
收藏
  |  
浏览/下载:22/0
  |  
提交时间:2022/12/23
Inductors
Topology
Switches
Power supplies
Switching frequency
Harmonic analysis
Buck converters
Interleaving parallel buck converter
International Thermonuclear Experimental Reactor (ITER)
large output capability
multilevel
static magnetic field (SMF) test facility
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
ENERGY REPORTS, 2022, 卷号: 8
作者:
Hua, Yuting
;
Fu, Peng
;
Huang, Liansheng
;
Li, Shenghu
收藏
  |  
浏览/下载:51/0
  |  
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
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:17/0
  |  
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
JOURNAL OF FUSION ENERGY, 2021, 卷号: 40
作者:
Zhang, Qiang
;
Song, Bo
;
Cai, Bin
;
Sun, Yuxiang
收藏
  |  
浏览/下载:53/0
  |  
提交时间:2021/11/16
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
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:57/0
  |  
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
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:49/0
  |  
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
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:60/0
  |  
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
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:47/0
  |  
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
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:27/0
  |  
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
IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2020, 卷号: 30
作者:
Wang, Xianwei
;
Xu, Aihua
;
Wang, Zhaoliang
收藏
  |  
浏览/下载:45/0
  |  
提交时间:2020/10/26
Central solenoid model coil (CSMC)
China fusion engineering test reactor (CFETR)
current lead joint
electromagnetic force
joggle
©版权所有 ©2017 CSpace - Powered by
CSpace