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Study on creep-fatigue life of ODS-Cu as heat sink in divertor PFU
期刊论文
FUSION ENGINEERING AND DESIGN, 2023, 卷号: 196
作者:
Zhang, Feng
;
Liu, Peng
;
Wang, Guodong
;
Cao, Qing
;
Mao, Xin
收藏
  |  
浏览/下载:8/0
  |  
提交时间:2023/11/17
Divertor
ODS-Cu
Heat sink
Creep-fatigue damage
Stress relaxation
Engineering design of the CFETR machine
期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 183
作者:
Song, Yuntao
;
Li, Jiangang
;
Wan, Yuanxi
;
Liu, Yong
;
Wang, Xiaolin
收藏
  |  
浏览/下载:23/0
  |  
提交时间:2022/12/22
CFETR
Engineering design
Tokamak
Magnetic confinement
Updates on CEA Design and Experimental Activities on EU DEMO TF System
期刊论文
IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2022, 卷号: 32
作者:
Zani, L.
;
Bonne, F.
;
Corato, V.
;
Decool, P.
;
Hertout, P.
收藏
  |  
浏览/下载:13/0
  |  
提交时间:2022/12/23
Conductors
Stress
Superconducting magnets
Toroidal magnetic fields
Europe
Costs
Windings
DEMO
LTS
Nb3Sn
nuclear fusion
super- conducting magnets
TF coils
SCELT (symbolic computation aided eigenvalue and linear code for tokamaks): A full MHD eigenvalue code in toroidal geometry developed with the use of a symbolic computation technique
期刊论文
COMPUTER PHYSICS COMMUNICATIONS, 2022, 卷号: 278
作者:
Ma, J.
;
Guo, W.
收藏
  |  
浏览/下载:14/0
  |  
提交时间:2022/12/23
Full MHD
Symbolic computation technique
Eigenvalue
Vector analysis
Automatic numerical discretization
Toroidal geometry
A new direct external recycling concept for the tritium fuel cycle of CFETR
期刊论文
INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2022, 卷号: 47
作者:
Cui, Shijie
;
Zheng, Shanliang
;
Lang, Yueheng
;
Chen, Junling
收藏
  |  
浏览/下载:12/0
  |  
提交时间:2022/12/23
CFETR
Tritium fuel cycle
Direct external recycling
Initial start-up inventory
Required TBR
Tritium self-sufficiency
Design of the Cooling Water System for the EAST Lower Divertor
期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2022
作者:
Zhou, Jinxuan
;
Hu, Jiansheng
;
Yang, Lei
;
Guo, Bin
;
Xu, Tiejun
收藏
  |  
浏览/下载:11/0
  |  
提交时间:2022/12/23
Valves
Thermal analysis
Heat transfer
Water heating
Plasma temperature
Tokamak devices
Heating systems
Cooling water system (CWS)
divertor
Experimental Advanced Superconducting Tokamak (EAST)
thermal-hydraulic analysis
water hammer
Seismic Analysis of the Vacuum Vessel for CFETR
期刊论文
FUSION SCIENCE AND TECHNOLOGY, 2022
作者:
Ni, Xiaojun
;
Han, Songbo
;
Ge, Jian
;
Sun, Jinxin
收藏
  |  
浏览/下载:23/0
  |  
提交时间:2022/05/05
CFETR
vacuum vessel
finite element
equivalent static analysis
response spectrum analysis
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:116/0
  |  
提交时间:2022/03/21
nuclear fusion
magnetic confinement
tokamak physics
divertor
WEST
ITER
DEMO
Progress in engineering design of CFETR toroidal field superconducting magnet
期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 177
作者:
Zheng, Jinxing
;
Song, Yuntao
;
Liu, Fei
;
Liu, Xufeng
;
Lu, Kun
收藏
  |  
浏览/下载:19/0
  |  
提交时间:2022/05/16
CFETR
TF coil case
TF winding pack
TF auxiliary structure
Preliminary design and analysis of the back supporting structure for CFETR WCCB blanket
期刊论文
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 177
作者:
Xu, Kun
;
Lei, Mingzhun
;
Xu, Shuling
;
Wu, Qigang
;
Liu, Sumei
收藏
  |  
浏览/下载:16/0
  |  
提交时间:2022/05/16
CFETR
BSS
Attachment
Thermal-hydraulic analysis
Mechanical analysis
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