机构

• 合肥物质科学研究院 [8]
• 兰州化学物理研究所 [2]

采集方式

• OAI收割 [10]

内容类型

• 期刊论文 [10]

发表日期

• 2020 [10]

学科主题

筛选

浏览/检索结果: 共10条，第1-10条 帮助 限定条件 发表日期：2020     条数/页： 5101520253035404550556065707580859095100 排序方式： 请选择提交时间升序提交时间降序发表日期升序发表日期降序题名升序题名降序作者升序作者降序 Influence of radiation defects on deuterium permeation behavior in tungsten 期刊论文  OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 542 作者:  Liu, Feng;  Zhou, Hai-Shan;  Xu, Chuan;  Cao, Xingzhong;  Ding, Fang   |  收藏  |  浏览/下载：60/0  |  提交时间：2020/12/28 Hydrogen isotopes  Tungsten  Radiation defects  Permeation  Diffusion   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：38/0  |  提交时间：2020/11/30 tungsten  deuterium plasma  high fluence  blister  deuterium retention   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：116/0  |  提交时间：2020/12/07 Oxide dispersion-strengthened  Pre-irradiation  Microstructure evolution  He+ ions  Deuterium retention   Deuterium retention characteristics in Li film by coating and during flowing liquid Li limiter operation in experimental advanced superconducting tokamak 期刊论文  OAI收割 Plasma Physics and Controlled Fusion, 2020, 卷号: 63 作者:  Li,C L;  Zuo,G Z;  Maingi,R;  Cao,Bin;  Xu,W   |  收藏  |  浏览/下载：32/0  |  提交时间：2020/12/28 wall retention  particle recycling  lithium  experimental advanced superconducting tokamak   Deuterium retention in tungsten and tungsten alloys exposed to pure and impurities seeding deuterium plasma 期刊论文  OAI收割 Nuclear materials and energy, 2020, 期号: 25, 页码: 100822 作者:  Hong Zhang;  Xuexi Zhang;  Li Qiao;  Peng Wang   |  收藏  |  浏览/下载：58/0  |  提交时间：2020/12/02 Influences of displacement damage due to heavy ion irradiation on deuterium retention in CLF-1 steel 期刊论文  OAI收割 Nuclear materials and energy, 2020, 期号: 25, 页码: 100794 作者:  Li Qiao;  Xuexi Zhang;  Ran He;  Hong Zhang;  Peng Wang   |  收藏  |  浏览/下载：28/0  |  提交时间：2020/12/02 Numerical Calculation on Recycling Ratio of Tritium from Tungsten Wall Used in Current CFETR Design 期刊论文  OAI收割 JOURNAL OF FUSION ENERGY, 2020 作者:  Yan, Qiang;  Chen, Zhongwen;  Wang, Zhijun;  Kong, Defeng;  Wang, Xiang   |  收藏  |  浏览/下载：30/0  |  提交时间：2020/11/26 Wall tritium recycling  Tungsten  Plasma material interaction  Fusion energy   The major trap sites of deuterium in CuCrZr alloy 期刊论文  OAI收割 NUCLEAR MATERIALS AND ENERGY, 2020, 卷号: 23 作者:  Liu, Hao-Dong;  Zhou, Hai-Shan;  Zhao, Si-Xiang;  Wang, Lu;  Wei, Ran   |  收藏  |  浏览/下载：96/0  |  提交时间：2020/11/30 Heat treatment  Hydrogen isotope  Retention  CuCrZr alloy   An in situ diagnostic method for monitoring of fuel retention on the first wall under long-pulse operation of experimental advanced superconducting tokamak 期刊论文  OAI收割 PHYSICA SCRIPTA, 2020, 卷号: T171 作者:  Li, Cong;  Sun, Liying;  Hu, Zhenhua;  Zhao, Dongye;  Liu, Jiamin   |  收藏  |  浏览/下载：26/0  |  提交时间：2021/04/26 plasma-wall interaction  fuel retention  tokamak  laser-induced breakdown spectroscopy   Net versus gross erosion of silicon carbide in DIII-D divertor 期刊论文  OAI收割 PHYSICA SCRIPTA, 2020, 卷号: T171 作者:  Rudakov, D. L.;  Wampler, W. R.;  Abrams, T.;  Ding, R.;  Boedo, J. A.   |  收藏  |  浏览/下载：23/0  |  提交时间：2020/11/26 DIII-D tokamak  DiMES  silicon carbide