中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
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浏览/检索结果: 共20条,第1-10条 帮助

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Effects of rhenium content on the deuterium permeation and retention behavior in tungsten 期刊论文  OAI收割
JOURNAL OF NUCLEAR MATERIALS, 2022, 卷号: 565
作者:  
Wu, Bo-Yu;  Xu, Yu-Ping;  Lyu, Yi-Ming;  Li, Xiao-Chun;  Geng, Xiang
  |  收藏  |  浏览/下载:38/0  |  提交时间:2022/12/23
In situ measurements of low energy D plasma-driven permeation through He pre-damaged W 期刊论文  OAI收割
NUCLEAR FUSION, 2022, 卷号: 62
作者:  
Li, Xue-Chun;  Zhou, Hai-Shan;  Liu, Hao-Dong;  Wang, Lu;  Luo, Guang-Nan
  |  收藏  |  浏览/下载:87/0  |  提交时间:2022/05/05
Deuterium retention and surface morphology modification in oxidized tungsten exposed to D plasma 期刊论文  OAI收割
INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2021, 卷号: 46
作者:  
Puyang, S. A.;  Lyu, Y. M.;  Nian, F. F.;  Xu, Y. P.;  Yang, Z. S.
  |  收藏  |  浏览/下载:41/0  |  提交时间:2021/11/01
Effect of N-2 on release behavior of D-2 in liquid lithium 期刊论文  OAI收割
NUCLEAR MATERIALS AND ENERGY, 2021, 卷号: 28
作者:  
Li, L.;  Zhang, D. H.;  Meng, X. C.;  Yuan, J. S.;  Huang, M.
  |  收藏  |  浏览/下载:32/0  |  提交时间:2021/11/01
Analyses of deuterium retention in tungsten and graphite first wall materials by laser-induced ablation spectroscopy on EAST 期刊论文  OAI收割
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 162
作者:  
Oelmann, Jannis;  Hu, Zhenhua;  Li, Cong;  Sun, Liying;  Liu, Jiamin
  |  收藏  |  浏览/下载:39/0  |  提交时间:2021/03/15
Blister-dominated retention mechanism in tungsten exposed to high-fluence deuterium plasma 期刊论文  OAI收割
NUCLEAR FUSION, 2020, 卷号: 60
作者:  
Liu, Mi;  Guo, Wangguo;  Cheng, Long;  Wang, Jun;  Wang, Shiwei
  |  收藏  |  浏览/下载:51/0  |  提交时间:2020/11/30
Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation 期刊论文  OAI收割
NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 卷号: 52
作者:  
Ding, Xiao-Yu;  Xu, Qiu;  Zhu, Xiao-yong;  Luo, Lai-Ma;  Huang, Jian-Jun
  |  收藏  |  浏览/下载:128/0  |  提交时间:2020/12/07
氘等离子体辐照下第一壁防护材料的刻蚀与燃料滞留行为研究 学位论文  OAI收割
北京: 中国科学院大学, 2019
作者:  
乔丽
  |  收藏  |  浏览/下载:133/0  |  提交时间:2019/10/31
TEM studies of 1 MeV Fe+ ion-irradiated W alloys by wet chemical method: high-temperature annealing and deuterium retention 期刊论文  OAI收割
NUCLEAR FUSION, 2019, 卷号: 59, 期号: 1, 页码: 12
作者:  
Ding, Xiao-Yu;  Liu, Jia-Qin;  Luo, Lai-Ma;  Xu, Qiu;  Gao, Xiang
  |  收藏  |  浏览/下载:82/0  |  提交时间:2019/01/11
Influence of surface melting on the deuterium retention in pure and lanthanum oxide doped tungsten 期刊论文  OAI收割
NUCLEAR FUSION, 2019, 卷号: 59, 期号: 1, 页码: 8
作者:  
Yuan, Yue;  Guo, Wangguo;  Wang, Peng;  Qu, Shilian;  Liu, Wei
  |  收藏  |  浏览/下载:35/0  |  提交时间:2019/12/25