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 [8]
力学研究所 [1]
采集方式
OAI收割 [9]
内容类型
期刊论文 [9]
发表日期
2022 [1]
2021 [2]
2020 [3]
2018 [2]
1991 [1]
学科主题
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Fishtail Divertor and its basis surface thermal load bearing performance
期刊论文
OAI收割
FUSION ENGINEERING AND DESIGN, 2022, 卷号: 180
作者:
Li, Yilong
;
Zhou, Tong
  |  
收藏
  |  
浏览/下载:12/0
  |  
提交时间:2022/12/23
Fishtail Divertor
Strike-line Swing
Thermophysical performance
Fusion reactor
Divertor
FRTHAM
FTD
A study on nuclear analysis of the divertor region of the CFETR
期刊论文
OAI收割
PLASMA SCIENCE & TECHNOLOGY, 2021, 卷号: 23
作者:
Saidahmed, Rayyan
;
Yao, Damao
;
Wu, Qiuran
;
Liu, Songlin
;
Xu, Tiejun
  |  
收藏
  |  
浏览/下载:66/0
  |  
提交时间:2021/11/15
CFETR
fusion reactor
divertor
nuclear analysis
divertor region
Critical Heat Flux (CHF) Correlations for Subcooled Water Flow Boiling at High Pressure and High Heat Flux
期刊论文
OAI收割
JOURNAL OF THERMAL SCIENCE, 2021, 卷号: 30
作者:
Liu, Ping
;
Guo, Yusheng
;
Ding, Wenlong
;
Tang, Mingyun
;
Song, Yuntao
  |  
收藏
  |  
浏览/下载:45/0
  |  
提交时间:2021/03/15
reactor divertor
correlations
subcooled water flow boiling
critical heat flux (CHF)
high heat flux
high pressure
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:71/0
  |  
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
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:53/0
  |  
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
Investigation on the Nuclear Heat Deposition of Shielding Blanket for CFETR Phase I
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48
作者:
Zhang, Jianzhong
;
Li, Jie
;
Zhang, Jie
;
Li, Lei
;
Qiu, Yang
  |  
收藏
  |  
浏览/下载:26/0
  |  
提交时间:2020/11/26
Computational fluid dynamics (CFD)
China Fusion Engineering Test Reactor (CFETR)
divertor
nuclear heat deposition
shielding blanket (SB)
Exploring the engineering limit of heat flux of a W/RAFM divertor target for fusion reactors
期刊论文
OAI收割
NUCLEAR FUSION, 2018, 卷号: 58, 期号: 6, 页码: 13
作者:
Mao, X.
;
Fursdon, M.
;
Chang, X. B.
;
Zhang, J. W.
;
Liu, P.
  |  
收藏
  |  
浏览/下载:27/0
  |  
提交时间:2019/06/03
reactor divertor
plasma facing unit
heat transfer coefficient
thermo-mechanical stress
fatigue life
Bree diagram
The Reliability Design of CFETR Divertor
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1402-1405
作者:
Cao, Lei
;
Zhou, Zibo
;
Zi, Pengfei
;
Yao, Damao
  |  
收藏
  |  
浏览/下载:12/0
  |  
提交时间:2019/06/03
Chinese fusion engineering testing reactor (CFETR)
divertor
mean time to failure (MTTF)
reliability
Jet:progress in performance and understanding
期刊论文
OAI收割
Plasma Physics and Controlled Fusion, 1991, 卷号: 33, 期号: 13, 页码: 1453-1477
作者:
The JET Team
收藏
  |  
浏览/下载:1156/57
  |  
提交时间:2009/08/03
Tokamak
Jet
Fusion Reactor
Particle Transport
Energy Transport
H-Mode Physics
Divertor Physics
Confinement
Plasmas
Temperature
Transport
Particle
Mode