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科研机构
合肥物质科学研究院 [12]
内容类型
期刊论文 [12]
发表日期
2022 [6]
2021 [1]
2020 [1]
2017 [1]
2016 [3]
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Evaluation of edge transport and core accumulation of tungsten for CFETR with EMC3-EIRENE and STRAHL
期刊论文
NUCLEAR FUSION, 2022, 卷号: 62
作者:
Liu, B.
;
Dai, S. Y.
;
Yang, X. D.
;
Chan, V. S.
;
Ding, R.
收藏
  |  
浏览/下载:16/0
  |  
提交时间:2022/12/22
tungsten distribution
CFETR
EMC3-EIRENE
STRAHL
Progress on physics understanding of improved confinement with fishbone instability at low q (95) < 3.5 operation regime in EAST
期刊论文
NUCLEAR FUSION, 2022, 卷号: 62
作者:
Zhang, B.
;
Gong, X.
;
Qian, J.
;
Zeng, L.
;
Xu, L. Q.
收藏
  |  
浏览/下载:18/0
  |  
提交时间:2022/12/23
confinement
ITER baseline
fishbone
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:15/0
  |  
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
Simulations of scrape-off layer power width for EAST H-mode plasma and ITER 15 MA baseline scenario by 2D electrostatic turbulence code
期刊论文
Nuclear Fusion, 2022, 卷号: 62
作者:
Liu,X.
;
Nielsen,A.H.
;
Rasmussen,J.J.
;
Naulin,V.
;
Wang,L.
收藏
  |  
浏览/下载:8/0
  |  
提交时间:2022/12/22
SOL power width
divertor
blob
turbulence
magnetic drift
ITER
DIII-D research advancing the physics basis for optimizing the tokamak approach to fusion energy
期刊论文
NUCLEAR FUSION, 2022, 卷号: 62
作者:
Fenstermacher, M. E.
;
Abbate, J.
;
Abe, S.
;
Abrams, T.
;
Adams, M.
收藏
  |  
浏览/下载:31/0
  |  
提交时间:2022/12/23
DIII-D
tokamak
fusion energy
plasma physics
core-edge integration
SOLPS-ITER simulations of high power exhaust for CFETR divertor with full drifts
期刊论文
NUCLEAR FUSION, 2022, 卷号: 62
作者:
Si, Hang
;
Ding, Rui
;
Senichenkov, Ilya
;
Rozhansky, Vladimir
;
Molchanov, Pavel
收藏
  |  
浏览/下载:17/0
  |  
提交时间:2022/05/05
divertor
power handling
modeling
CFETR
Impact of neutron irradiation on hardening of baseline and advanced tungsten grades and its link to initial microstructure
期刊论文
Nuclear Fusion, 2021, 卷号: 61
作者:
Yin,Chao
;
Terentyev,Dmitry
;
Dubinko,Andrii
;
Zhang,Tao
;
Wirtz,Marius
收藏
  |  
浏览/下载:77/0
  |  
提交时间:2021/05/24
tungsten
neutron irradiation
irradiation hardening
microindentation
Scaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks
期刊论文
NUCLEAR FUSION, 2020, 卷号: 60
作者:
Horacek, J.
;
Adamek, J.
;
Komm, M.
;
Seidl, J.
;
Vondracek, P.
收藏
  |  
浏览/下载:26/0
  |  
提交时间:2020/11/26
tokamak
L-mode
divertor
scaling
heat flux
ITER
COMPASS-Upgrade
Fatigue performance evaluation for ITER IVC conductor component materials
期刊论文
VACUUM, 2017, 卷号: 145, 期号: 无, 页码: 86-94
作者:
Jin, H.
;
Vostner, A.
;
Wu, Y.
;
Macioce, D.
;
Sgobba, S.
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2019/02/28
OFE conductor
SS316LN
Cold working
Aging
S-N curve
ITER vacuum vessel structural analysis completion during manufacturing phase
期刊论文
FUSION ENGINEERING AND DESIGN, 2016, 卷号: 109, 期号: 无, 页码: 688-692
作者:
Martinez, J. -M.
;
Alekseev, A.
;
Sborchia, C.
;
Choi, C. H.
;
Utin, Y.
收藏
  |  
浏览/下载:23/0
  |  
提交时间:2017/12/18
Iter
Vacuum Vessel
Nuclear Pressure Equipment
Structural Integrity
Analysis
Manufacturing Design
Rcc-mr
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