中文版 | English

在结果中检索

HFCAS OpenIR

浏览/检索结果: 共189条，第1-10条 帮助

已选(0)清除 条数/页：   排序方式：
Deuterium erosion and retention properties on MoAlB ceramics by ion irradiation 期刊论文
VACUUM, 2023, 卷号: 207
作者:  Li, Cong;  Tu, Hanjun;  Zhang, Dongya;  Zhu, Dahuan;  Shi, Liqun
收藏  |  浏览/下载：28/0  |  提交时间：2022/12/23
Deuterium concentration  Sputtering yield  Erosion  TRIDYN  
Preliminary exploration of a WTaVTiCr high-entropy alloy as a plasma-facing material 期刊论文
NUCLEAR FUSION, 2022, 卷号: 62
作者:  Li, Yu;  Sun, Yuhan;  Cheng, Long;  Yuan, Yue;  Jia, Baohai;  He, Jiaqing;  Lu, Guang-Hong;  Luo, Guang-Nan;  Zhu, Qiang
收藏  |  浏览/下载：42/0  |  提交时间：2022/12/22
high-entropy alloys  plasma-facing materials  nuclear fusion  
The effect of He-induced surface microstructure on D plasma-driven permeation through RAFM steel 期刊论文
Nuclear Fusion, 2022, 卷号: 62
作者:  Wang,Lu;  Zhou,Hai-Shan;  Liu,Hao-Dong;  Qi,Qiang;  Tu,Han-Jun;  Shi,Li-Qun;  Luo,Guang-Nan
收藏  |  浏览/下载：31/0  |  提交时间：2022/12/22
RAFM steel  deuterium  permeation  helium bubble  helium exposure  
Experimental research on ammonia concentration detection with white light-emitting diodes 期刊论文
JOURNAL OF OPTICAL TECHNOLOGY, 2021, 卷号: 88
作者:  Zhang, K.;  Lu, H-B;  Shao, L.;  Zheng, C.;  Zhang, Y-J;  Huang, S-Y
收藏  |  浏览/下载：48/0  |  提交时间：2021/11/01
Plasma-surface interaction experimental device: PSIEC and its first plasma exposure experiments on bulk tungsten and coatings 期刊论文
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 164
作者:  Xu, Yue;  Xu, Yunfeng;  Wu, Zuosheng;  Luo, Laima;  Zan, Xiang;  Yao, Gang;  Xi, Ya;  Wang, Yafeng;  Ding, Xiaoyu;  Bi, Hailin;  Zhu, Xiaoyong;  Xu, Qiu;  Wu, Jiefeng;  Wu, Yucheng
收藏  |  浏览/下载：33/0  |  提交时间：2021/05/06
Linear plasma device  Plasma-Material interaction  Plasma-Facing material  Tungsten  
Effect of tungsten deposition thickness on hydrogen isotope permeation through RAFM steel 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2021, 卷号: 545
作者:  Liu, Hao-Dong;  Zhou, Hai-Shan;  Qiao, Li;  Zhang, Hong;  Luo, Guang-Nan
收藏  |  浏览/下载：66/0  |  提交时间：2021/03/15
Tungsten  RAFM steel  Hydrogen isotope  Permeation  
Simulation studies of divertor power exhaust with neon seeding for CFETR with GW-level fusion power 期刊论文
PHYSICS OF PLASMAS, 2020, 卷号: 27
作者:  Liu, X. J.;  Xu, G. L.;  Ding, R.;  Jia, G. Z.;  Sang, C. F.;  Si, H.;  Nian, F. F.;  Yang, Z. S.;  Li, G. Q.;  Chan, V. S.;  Deng, G. Z.;  Gao, S. L.;  Gao, X.
收藏  |  浏览/下载：45/0  |  提交时间：2020/11/30
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
NUCLEAR FUSION, 2020, 卷号: 60
作者:  Xu, G. S.;  Yuan, Q. P.;  Li, K. D.;  Wang, L.;  Xu, J. C.;  Yang, Q. Q.;  Duan, Y. M.;  Meng, L. Y.;  Yang, Z. S.;  Ding, F.;  Liu, J. B.;  Guo, H. Y.;  Wang, H. Q.;  Eldon, D.;  Tao, Y. Q.;  Wu, K.;  Yan, N.;  Ding, R.;  Wang, Y. F.;  Ye, Y.;  Zhang, L.;  Zhang, T.;  Zang, Q.;  Li, Y. Y.;  Liu, H. Q.;  Jia, G. Z.;  Liu, X. J.;  Si, H.;  Li, E. Z.;  Zeng, L.;  Qian, J. P.;  Lin, S. Y.;  Xu, L. Q.;  Wang, H. H.;  Gong, X. Z.;  Wan, B. N.
浏览  |  Adobe PDF(4069Kb)  |  收藏  |  浏览/下载：654/34  |  提交时间：2020/10/22
divertor impurity seeding  radiative divertor feedback control  partial detachment  grassy-ELM H-mode regime  tokamak  
Numerical Calculation on Recycling Ratio of Tritium from Tungsten Wall Used in Current CFETR Design 期刊论文
JOURNAL OF FUSION ENERGY, 2020
作者:  Yan, Qiang;  Chen, Zhongwen;  Wang, Zhijun;  Kong, Defeng;  Wang, Xiang;  Gou, Fujun;  Zhang, Kun
收藏  |  浏览/下载：46/0  |  提交时间：2020/11/26
Wall tritium recycling  Tungsten  Plasma material interaction  Fusion energy  
Simulations of Ar seeding by SOLPS-ITER for a slot-type divertor concept 期刊论文
PHYSICS OF PLASMAS, 2020, 卷号: 27
作者:  Jia, Guozhang;  Liu, Xiaoju;  Xu, Guosheng;  Wang, Liang;  Zhu, Sizheng;  Xie, Hai;  Si, Hang;  Sang, Chaofeng;  Yang, Zhongshi;  Xu, Jichan;  Li, Hang
收藏  |  浏览/下载：23/0  |  提交时间：2020/10/21