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 [9]
力学研究所 [2]
广州能源研究所 [2]
采集方式
OAI收割 [13]
内容类型
期刊论文 [13]
发表日期
2020 [13]
学科主题
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Metallic impurity content behavior during ICRH-heated L-mode discharges in EAST
期刊论文
OAI收割
NUCLEAR FUSION, 2020, 卷号: 60
作者:
Urbanczyk, G.
;
Zhang, X. J.
;
Zhang, L.
;
Colas, L.
;
Dumont, R.
  |  
收藏
  |  
浏览/下载:36/0
  |  
提交时间:2020/11/30
ICRH
RF sheath
near field
far field
impurity
tungsten
heat loads
Interface design of the blanket system for CFETR
期刊论文
OAI收割
NUCLEAR FUSION, 2020, 卷号: 60
作者:
Lei, Mingzhun
;
Song, Yuntao
;
Ni, Xiaojun
;
Wu, Xinghua
;
Shen, Junsong
  |  
收藏
  |  
浏览/下载:47/0
  |  
提交时间:2020/11/30
CFETR
interface design
blanket system
integration
Effect of device models on the multiobjective optimal operation of CCHP microgrids considering shiftable loads
期刊论文
OAI收割
APPLIED ENERGY, 2020, 卷号: 275, 页码: 19
作者:
Cui, Qiong
;
Ma, Peipei
;
Huang, Lei
;
Shu, Jie
;
Luv, Jie
  |  
收藏
  |  
浏览/下载:18/0
  |  
提交时间:2020/10/30
CCHP microgrid
Shiftable loads
Partial load ratio model
Constant efficiency model
Multiple optimization objectives
Heat-to-electricity ratio
Summary of the 3rd IAEA technical meeting on divertor concepts
期刊论文
OAI收割
NUCLEAR FUSION, 2020, 卷号: 60
作者:
Barbarino, Matteo
;
Leonard, Anthony
;
Asakura, Nobuyuki N.
;
Jakubowski, Marcin
;
Kobayashi, Masahiro
  |  
收藏
  |  
浏览/下载:32/0
  |  
提交时间:2020/10/26
divertor and confinement
radiative power exhaust
scrape-off layer and divertor physics
steady state operation and transient heat loads
plasma facing components materials and heat exhaust for steady state operation
divertors for DEMO and reactors
The simulation of the application of quasi-snowflake magnetic configuration on the EAST new lower tungsten divertor
期刊论文
OAI收割
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 158
作者:
Zhang, Chen
;
Sang, Chaofeng
;
Wang, Liang
;
Luo, Zhengping
;
Xu, Guosheng
  |  
收藏
  |  
浏览/下载:24/0
  |  
提交时间:2020/11/30
EAST
SOLPS-ITER
Quasi-snowflake divertor
Neon seeding
Numerical simulations of NBI fast ion loss with RMPs on the EAST tokamak
期刊论文
OAI收割
NUCLEAR FUSION, 2020, 卷号: 60
作者:
Xu, Yingfeng
;
Li, Li
;
Hu, Youjun
;
Liu, Yueqiang
;
Guo, Wenfeng
  |  
收藏
  |  
浏览/下载:56/0
  |  
提交时间:2020/10/26
resonant magnetic perturbation
neutral beam injection
fast ion loss
orbit-following code
EAST
Divertor impurity seeding with a new feedback control scheme for maintaining good core confinement in grassy-ELM H-mode regime with tungsten monoblock divertor in EAST
期刊论文
OAI收割
NUCLEAR FUSION, 2020, 卷号: 60
作者:
Xu, G. S.
;
Yuan, Q. P.
;
Li, K. D.
;
Wang, L.
;
Xu, J. C.
  |  
收藏
  |  
浏览/下载:60/0
  |  
提交时间:2020/10/22
divertor impurity seeding
radiative divertor feedback control
partial detachment
grassy-ELM H-mode regime
tokamak
Simulations of first-orbit losses of neutral beam injection (NBI) fast ions on EAST
期刊论文
OAI收割
PLASMA SCIENCE & TECHNOLOGY, 2020, 卷号: 22
作者:
Xu, Xingyuan
;
Xu, Yingfeng
;
Zhang, Xiaodong
;
Hu, Youjun
;
Ye, Lei
  |  
收藏
  |  
浏览/下载:18/0
  |  
提交时间:2020/11/26
neutral beam
first-orbit loss
GYCAVA
Test Facility and Results of ITER PF4 Current Leads
期刊论文
OAI收割
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48
作者:
Du, Q.
;
Liu, C.
;
Ding, K.
;
Lu, K.
;
Long, Y.
  |  
收藏
  |  
浏览/下载:37/0
  |  
提交时间:2020/10/21
High-temperature superconductors
Test facilities
Heating systems
Plasma temperature
Prototypes
Steady-state
Resistance
International Thermonuclear Experimental Reactor (ITER)
performance test
PF4 high-temperature superconducting (HTS) current leads
test facility
Performance and Modeling of a Two-Stage Light Gas Gun Driven by Gaseous Detonation
期刊论文
OAI收割
APPLIED SCIENCES-BASEL, 2020, 卷号: 10, 期号: 12, 页码: 16
作者:
Tang WQ(唐伟奇)
;
Wang Q(汪球)
;
Wei BC(魏炳忱)
;
Li JW(栗继伟)
;
Li JP(李进平)
  |  
收藏
  |  
浏览/下载:71/0
  |  
提交时间:2020/08/26
two-stage light gas gun
detonation
quasi-one-dimensional
piston
projectile