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 [10]
金属研究所 [1]
采集方式
OAI收割 [11]
内容类型
期刊论文 [11]
发表日期
2024 [2]
2020 [3]
2019 [1]
2018 [4]
2013 [1]
学科主题
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An innovative approach to effective breeding blanket design for future fusion reactors
期刊论文
OAI收割
PLASMA SCIENCE & TECHNOLOGY, 2024, 卷号: 26
作者:
Liu, Changle
;
Li, Lei
;
He, Yanzi
;
Zhang, Peng
;
Zhou, Yu
  |  
收藏
  |  
浏览/下载:7/0
  |  
提交时间:2024/11/20
TBR
tritium release
temperature field
blanket design
fusion reactor
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:12/0
  |  
提交时间:2024/11/22
China Fusion Engineering Test Reactor (CFETR) toroidal field (TF) coil
design
lifting process
strength analysis
Preliminary Design Progress of the CFETR Water-Cooled Divertor
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48
作者:
Qin, Shijun
;
Yao, Damao
;
Wang, Qingfeng
;
Mao, Xin
;
Liu, Peng
  |  
收藏
  |  
浏览/下载:58/0
  |  
提交时间:2020/10/26
Cooling
Plasma temperature
Thermal analysis
Heating systems
Heat engines
Stress
Chinese Fusion Engineering and Testing Reactor (CFETR)
design and analysis
divertor
water-cooled
Rotary Joint Design for High Payload Remote Handling System for a Tokamak Reactor
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48
作者:
Bai, Xiaowei
;
Zhou, Zibo
;
Wang, Yan
;
Yao, Damao
;
Choi, Chang-Hwan
  |  
收藏
  |  
浏览/下载:29/0
  |  
提交时间:2020/10/29
Gears
Payloads
Torque
Loading
Stress
Servomotors
Inductors
China fusion engineering test reactor (CFETR)
cycloid gearbox
design requirements
high payload
remote handling (RH)
rotary joint
three-stage reducers
Strategy Study and Preliminary Conceptual Design of the Remote Maintenance Systems for in Vessel Components of CFETR
期刊论文
OAI收割
JOURNAL OF FUSION ENERGY, 2020
作者:
Zhao, Wenlong
;
Shi, Shanshuang
;
Cheng, Yong
;
Huang, Jianjun
;
Sun, Huibin
  |  
收藏
  |  
浏览/下载:42/0
  |  
提交时间:2020/11/26
CFETR
Fusion reactor
Remote maintenance
Tokamak design
Compatibility
Structural Design and Analysis of the Feeder in the CFETR CS Model Coil Cryogenic Test Facility
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2019, 卷号: 47, 期号: 1, 页码: 897-901
作者:
Guo, Liang
;
Wu, Yu
;
Liu, Huajun
  |  
收藏
  |  
浏览/下载:16/0
  |  
提交时间:2020/03/31
Central solenoid model coil (CSMC)
Chinese fusion engineering testing reactor (CFETR)
feeder structural design
finite-element (FE) analysis
test platform
CFETR integration design platform: Development of space analysis module
期刊论文
OAI收割
FUSION ENGINEERING AND DESIGN, 2018, 卷号: 134, 页码: 29-34
作者:
Deng, J. S.
;
Zhu, Z. Y.
;
Li, Y.
;
Wang, Z. W.
;
Mao, S. F.
  |  
收藏
  |  
浏览/下载:82/0
  |  
提交时间:2019/12/20
Integrated design
Space analysis
Deformation
Fusion reactor
CFETR
Tokamak Design and Maintenance Scheme Tradeoff Application on CFETR
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1156-1165
作者:
Villedieu, E.
;
Song, Y. T.
;
Cheng, Y.
;
Zhan, J.
;
Dechelle, C.
  |  
收藏
  |  
浏览/下载:33/0
  |  
提交时间:2019/08/23
Fusion reactor design
maintenance
remote handling
tokamak
Winding Design for CFETR Central Solenoid Model Coil
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1522-1527
作者:
Han, Houxiang
;
Wu, Yu
;
Yin, Dapeng
;
Qin, Jinggang
;
Shi, Yi
  |  
收藏
  |  
浏览/下载:31/0
  |  
提交时间:2019/08/23
Cable-in-conduit conductor (CICC)
central solenoid model coil (CSMC)
China Fusion Engineering Test Reactor (CFETR)
pancake coil
superconducting magnets
winding design
Conceptual Design of CFETR CS Model Coil Structure
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1507-1511
作者:
Yin, Dapeng
;
Wu, Yu
;
Han, Houxiang
;
Xu, Aihua
;
Hao, Qiangwang
  |  
收藏
  |  
浏览/下载:62/0
  |  
提交时间:2019/08/23
Cable-in-conduit conductor (CICC)
central solenoid (CS) model coil
China fusion engineering test reactor (CFETR)
structural concept design
superconducting magnets