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合肥物质科学研究院 [12]
清华大学 [1]
大连理工大学 [1]
上海电子信息职业技术... [1]
西安理工大学 [1]
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期刊论文 [16]
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2022 [3]
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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:17/0
  |  
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
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.
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  |  
浏览/下载:120/0
  |  
提交时间:2022/03/21
nuclear fusion
magnetic confinement
tokamak physics
divertor
WEST
ITER
DEMO
Status of the WEST travelling wave array antenna design and results from the high power mock-up
期刊论文
NUCLEAR FUSION, 2022, 卷号: 62
作者:
Ragona, R.
;
Durodie, F.
;
Messiaen, A.
;
Ongena, J.
;
Van Schoor, M.
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  |  
浏览/下载:49/0
  |  
提交时间:2022/02/14
travelling wave
ICRH
combline
WEST
DEMO
Design and thermal-structural analysis of a high power ICRH travelling wave array antennas
期刊论文
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 166
作者:
Batal, T.
;
Ragona, R.
;
Hillairet, J.
;
Yu, C.
;
Bernard, J-M
收藏
  |  
浏览/下载:59/0
  |  
提交时间:2021/06/15
Travelling wave antenna
Heating system
Ion cyclotron resonance heating
DEMO
Virtual reality
Thermal and structural analysis
New designs of target and cooling scheme for water cooled divertor in DEMO
期刊论文
NUCLEAR FUSION, 2021, 卷号: 61
作者:
Qian, X. Y.
;
Peng, X. B.
;
Song, Y. T.
;
Mao, X.
;
Liu, P.
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  |  
浏览/下载:35/0
  |  
提交时间:2021/03/15
DEMO
divertor
water cooled target
cooling circuit
structural design
thermal-hydraulics
Summary of the 3rd IAEA technical meeting on divertor concepts
期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:
Barbarino, Matteo
;
Leonard, Anthony
;
Asakura, Nobuyuki N.
;
Jakubowski, Marcin
;
Kobayashi, Masahiro
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  |  
浏览/下载:61/0
  |  
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
Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors
期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:
Liu, Xiaogang
;
Wu, Fan
;
Wang, Zhaoliang
;
Li, Guoqiang
;
Liu, Xiaoju
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  |  
浏览/下载:51/0
  |  
提交时间:2020/11/26
tokamak
DEMO
superconducting magnet
TF
cable-in-conduit conductor
electromagnetic load
mechanical analysis
EMC3-EIRENE modeling of edge plasma to improve the ICRF coupling with local gas puffing in DEMO
期刊论文
NUCLEAR FUSION, 2018, 卷号: 58, 期号: 12, 页码: 11
作者:
Zhang, Wei
;
Franke, Thomas
;
Noterdaeme, Jean-Marie
;
Van Eester, Dirk
收藏
  |  
浏览/下载:16/0
  |  
提交时间:2019/12/20
scrape-off layer
ICRF coupling
DEMO
local gas puffing
Investigation on the Effect of Tritium Breeding Ratio Using Temperature Control Mechanism for DEMO Blanket
期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 6, 页码: 2277-2280
作者:
Qiu, Yang
;
Zhang, Jie
;
Liu, Changle
;
Yao, Damao
;
Gao, Xiang
收藏
  |  
浏览/下载:16/0
  |  
提交时间:2019/11/12
Breeding blanket
demonstrate power plant (DEMO)
temperature control mechanism (TCM)
tritium breeding ratio (TBR)
Current Status and Progress on the Shielding Blanket of CFETR
期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1417-1421
作者:
Liu, Changle
;
Yang, Hao
;
Zhang, Jie
;
Zhang, Jianzhong
;
Li, Lei
收藏
  |  
浏览/下载:9/0
  |  
提交时间:2019/08/23
Chinese fusion engineering test reactor (CFETR)
demonstration reactors (DEMO)
neutronics
shielding blanket (SB)
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