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 [21]
采集方式
OAI收割 [21]
内容类型
期刊论文 [21]
发表日期
2021 [5]
2020 [7]
2018 [4]
2017 [2]
2016 [3]
学科主题
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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:56/0
  |  
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:29/0
  |  
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:24/0
  |  
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:28/0
  |  
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:16/0
  |  
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:55/0
  |  
提交时间:2020/10/26
Central solenoid model coil (CSMC)
China fusion engineering test reactor (CFETR)
current lead joint
electromagnetic force
joggle
Dynamic analysis of multi-functional maintenance platform based on Newton-Euler method and improved virtual work principle
期刊论文
OAI收割
NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 卷号: 52
作者:
Li, Dongyi
;
Lu, Kun
;
Cheng, Yong
;
Zhao, Wenlong
;
Yang, Songzhu
  |  
收藏
  |  
浏览/下载:55/0
  |  
提交时间:2020/11/30
China Fusion engineering test reactor
Divertor
Multi-functional maintenance platform
3-RPS parallel Robot
Dynamic analysis
ADAMS simulation
Design of Test Platform of High-Payload Transporter Joint for a Tokamak
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48
作者:
Wang, Yan
;
Zhou, Zibo
;
Bai, Xiaowei
;
Yao, Damao
;
Choi, Chang-Hwan
  |  
收藏
  |  
浏览/下载:26/0
  |  
提交时间:2020/10/26
Hydraulic systems
Loading
Shafts
Torque
Force
Couplings
Servomotors
China fusion engineering test reactor (CFETR)
International Thermonuclear Experimental Reactor (ITER)
remote handling (RH)
test platform
A Reliability Analysis of CFETR CSMC Heat Treatment System Based on RPN-HAZOP Method
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48
作者:
Wang, Weijun
;
Qin, Jinggang
;
Yu, Min
;
Li, Tong
;
Song, Jian
  |  
收藏
  |  
浏览/下载:23/0
  |  
提交时间:2020/10/29
Heat treatment
Reliability
Furnaces
Superconducting coils
Fans
Plasma temperature
Superconducting magnets
The China Fusion Engineering Test Reactor (CFETR)
heat treatment
reliability analysis
superconducting coil
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:16/0
  |  
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