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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:30/0  |  提交时间:2022/12/23
Deuterium concentration  Sputtering yield  Erosion  TRIDYN  
The influence of deuterium ions on the deuterium permeation and retention behavior in V-4Cr-4Ti alloy under plasma loading 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2021, 卷号: 554
作者:  Liu, Haodong;  Zhou, Hai-Shan;  Luo, Guang-Nan;  Zheng, Peng-Fei
收藏  |  浏览/下载:112/0  |  提交时间:2021/08/30
Hydrogen isotope  Permeation  Retention  V-4Cr-4Ti alloy  
The major trap sites of deuterium in CuCrZr alloy 期刊论文
NUCLEAR MATERIALS AND ENERGY, 2020, 卷号: 23
作者:  Liu, Hao-Dong;  Zhou, Hai-Shan;  Zhao, Si-Xiang;  Wang, Lu;  Wei, Ran;  Luo, Guang-Nan
收藏  |  浏览/下载:35/0  |  提交时间:2020/11/30
Heat treatment  Hydrogen isotope  Retention  CuCrZr alloy  
Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR 期刊论文
FUSION ENGINEERING AND DESIGN, 2020, 卷号: 153
作者:  Huang, Kai;  Zhao, Xueli;  Ma, Xuebin;  Liu, Songlin
收藏  |  浏览/下载:54/0  |  提交时间:2020/11/26
Tritium transport  System level  WCCB blanket  CFETR  
Summary of the 8th Asia-Pacific Transport Working Group (APTWG) Meeting 期刊论文
NUCLEAR FUSION, 2019, 卷号: 59, 期号: 4, 页码: 14
作者:  Shi, Z. B.;  Cheng, J.;  Xu, Y. H.;  Tokuzawa, T.;  Qiu, Z. Y.;  Sasaki, M.;  Zhong, W. L.;  Ida, K.;  Wang, Z. X.;  Zhang, T.;  Kim, J.;  Kwon, J. M.;  Kobayashi, T.;  Lee, W. C.
浏览  |  Adobe PDF(463Kb)  |  收藏  |  浏览/下载:108/54  |  提交时间:2020/03/31
turbulence  transport  conference  APTWG  plasma  
Effect of deuterium on bonding quality of W/Ti/Steel HIP joints in first wall application 期刊论文
FUSION ENGINEERING AND DESIGN, 2019, 卷号: 138, 期号: 无, 页码: 313-320
作者:  Wang, Ji-Chao;  Huang, Jianjun;  Sun, Huibin;  Gao, Xiang;  Wang, Wanjing;  Li, Qiang;  Xie, Chunyi;  Wang, Xingli;  Chen, Zhen;  Gao, Qingran;  Liu, Songlin;  Luo, Guang-Nan;  Li, Jiangang
浏览  |  Adobe PDF(3970Kb)  |  收藏  |  浏览/下载:80/44  |  提交时间:2020/05/21
W steel  H isotope  Diffusion bonding  CFETR  WCCB  
Estimation of carbon impurity from the guard limiter of the lower hybrid wave antenna on EAST tokamak 期刊论文
PLASMA PHYSICS AND CONTROLLED FUSION, 2018, 卷号: 60, 期号: 12, 页码: 11
作者:  Ou, Jing;  Xiang, Nong;  Liu, Liang;  Men, Zongzheng;  Zhang, Ling;  Mao, Songtao;  Chen, Meiwen
Adobe PDF(1532Kb)  |  收藏  |  浏览/下载:111/55  |  提交时间:2019/01/11
physical sputtering  chemical erosion  hot spot  plasma sheath  
Modeling of fuel retention in the upper tungsten divertor of EAST from attached to detached divertor plasma 期刊论文
FUSION ENGINEERING AND DESIGN, 2018, 卷号: 136, 页码: 908-913
作者:  Sang, Chaofeng;  Wang, Zhenhou;  Wang, Liang;  Ding, Rui;  Wang, Qi;  Sun, Jizhong;  Wang, Dezhen
收藏  |  浏览/下载:45/0  |  提交时间:2019/12/25
Retention  Divertor  Tungsten  Modeling