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Conceptual design and heat transfer performance of a flat-tile water-cooled divertor target 期刊论文
PLASMA SCIENCE & TECHNOLOGY, 2021, 卷号: 23
作者:  LI, Lei;  Han, Le;  Zi, Pengfei;  Cao, Lei;  Xu, Tiejun;  Mou, Nanyu;  Wang, Zhaoliang;  Yin, Lei;  Yao, Damao
收藏  |  浏览/下载：50/0  |  提交时间：2021/08/30
CFETR  heat transfer performance  parametric design and optimization  HHF tests  flat-tile divertor target  
Impact of W monoblock damage on EAST operations in recent campaigns 期刊论文
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 169
作者:  Binfu, Gao;  Rui, Ding;  Ling, Zhang;  Changjun, Li;  Hai, Xie;  Long, Zeng;  Jianhua, Yang;  Baoguo, Wang;  Dahuan, Zhu;  Junling, Chen
收藏  |  浏览/下载：57/0  |  提交时间：2021/08/30
W monoblock damage  Melting  Cracking  Arcing  Disruption  
Deuterium retention characteristics in Li film by coating and during flowing liquid Li limiter operation in experimental advanced superconducting tokamak 期刊论文
Plasma Physics and Controlled Fusion, 2020, 卷号: 63
作者:  Li,C L;  Zuo,G Z;  Maingi,R;  Cao,Bin;  Xu,W;  Meng,X C;  Sun,Z;  Huang,M;  Tang,Z L;  Zhang,D H;  Qian,Y Z;  Andruczyk,D;  Tritz,K;  Hu,J S
收藏  |  浏览/下载：41/0  |  提交时间：2020/12/28
wall retention  particle recycling  lithium  experimental advanced superconducting tokamak  
Development of a new TZM substrate flowing liquid lithium limiter for high performance plasma discharge in EAST 期刊论文
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 158
作者:  Li, C. L.;  Zuo, G. Z.;  Maingi, R.;  Meng, X. C.;  Xu, W.;  Sun, Z.;  Qian, Y. Z.;  Huang, M.;  Andruczyk, D.;  Tritz, K.;  Hu, J. S.
收藏  |  浏览/下载：60/0  |  提交时间：2020/11/30
Liquid Li  TZM alloy  Limiter  EAST  
Results from a new flowing liquid Li limiter with TZM substrate during high confinement plasmas in the EAST device 期刊论文
Physics of Plasmas, 2020, 卷号: 27
作者:  Zuo, G.Z;  Hu, J.S
收藏  |  浏览/下载：28/0  |  提交时间：2020/10/23
Improvement on the plasma performances via application of flowing lithium limiters in EAST tokamak 期刊论文
PHYSICA SCRIPTA, 2020, 卷号: T171
作者:  Zuo, G. Z.;  Hu, J. S.;  Maingi, R.;  Li, C. L.;  Meng, X. C.;  Sun, Z.;  Huang, M.;  Xu, W.;  Qian, Y. Z.;  Andruczyk, D.;  Tritz, K.;  Gong, X. Z.;  Li, J. G.
收藏  |  浏览/下载：52/0  |  提交时间：2020/11/26
flowing liquid Li  Li surface coverage  surface erosion  plasma performance  EAST  
Experiments of continuously and stably flowing lithium limiter in EAST towards a solution for the power exhaust of future fusion devices 期刊论文
NUCLEAR MATERIALS AND ENERGY, 2019, 卷号: 18, 期号: 无, 页码: 99-104
作者:  Hu, J. S.;  Zuo, G. Z.;  Maingi, R.;  Sun, Z.;  Tritz, K.;  Xu, W.;  Yang, Q. X.;  Andruczyk, D.;  Huang, M.;  Meng, X. C.;  Gong, X. Z.;  Ruzic, D. N.;  Ni, M. J.;  Wan, B. N.;  Li, J. G.
浏览  |  Adobe PDF(1664Kb)  |  收藏  |  浏览/下载：4104/33  |  提交时间：2020/07/14
Limiter  Lithium  Plasma facing component  EAST  
Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST 期刊论文
NUCLEAR FUSION, 2019, 卷号: 59, 期号: 1, 页码: 11
作者:  Zuo, G. Z.;  Hu, J. S.;  Maingi, R.;  Sun, Z.;  Yang, Q. X.;  Huang, M.;  Meng, X. C.;  Xu, W.;  Qian, Y. Z.;  Li, C. L.;  Bi, H. L.;  Chen, Y.;  Yuan, X. L.;  Han, X. F.;  Zhu, X.;  Wang, Y. F.;  Zhang, L.;  Liu, H. Q.;  Wang, L.;  Gong, X. Z.;  Tritz, K.;  Diallo, A.;  Lunsford, R.;  Ni, M. J.;  Li, J. G.
收藏  |  浏览/下载：41/0  |  提交时间：2019/12/25
liquid Li  Li uniformity  heat flux  high power plasma  edge localized mode  
Design of Langmuir probe diagnostic system for the upgraded lower tungsten divertor in EAST tokamak 期刊论文
REVIEW OF SCIENTIFIC INSTRUMENTS, 2018, 卷号: 89, 期号: 10, 页码: 5
作者:  Xu, J. C.;  Wang, L.;  Xu, G. S.;  Zhu, D. H.;  Feng, W.;  Liu, J. B.;  Deng, G. Z.;  Lan, H.;  Yao, D. M.;  Luo, G. N.;  Guo, H. Y.
Adobe PDF(2034Kb)  |  收藏  |  浏览/下载：150/97  |  提交时间：2019/01/11
The Feasibility of Application of the Existing IVVS Concept to CFETR 期刊论文
IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 6, 页码: 2203-2206
作者:  Zhou, Zibo;  Cao, Lei;  Xu, Houchang;  Yao, Damao
浏览  |  Adobe PDF(1843Kb)  |  收藏  |  浏览/下载：88/40  |  提交时间：2019/11/12
Chinese Fusion Engineering Test Reactor (CFETR)  cylindrical vessel  Experimental Advanced Superconducting Tokamak (EAST)  in-vessel viewing system (IVVS)