机构

• 合肥物质科学研究院 [15]
• 金属研究所 [1]
• 宁波材料技术与工程研... [1]
• 沈阳自动化研究所 [1]
• 近代物理研究所 [1]

采集方式

• OAI收割 [19]

内容类型

• 期刊论文 [19]

发表日期

• 2020 [19]

学科主题

• Materials ... [1]
• Science & ... [1]

筛选

浏览/检索结果: 共19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   R&D achievements for vacuum vessel towards CFETR construction 期刊论文  OAI收割 NUCLEAR FUSION, 2020, 卷号: 60 作者:  Liu, Zhihong;  Ji, Haibiao;  Wu, Jiefeng;  Wu, Huapeng;  Ma, Jianguo   |  收藏  |  浏览/下载：95/0  |  提交时间：2020/11/30 CFETR  vacuum vessel  sector  fabrication   Summary of the 3rd IAEA technical meeting on divertor concepts 期刊论文  OAI收割 NUCLEAR FUSION, 2020, 卷号: 60 作者:  Barbarino, Matteo;  Leonard, Anthony;  Asakura, Nobuyuki N.;  Jakubowski, Marcin;  Kobayashi, Masahiro   |  收藏  |  浏览/下载：33/0  |  提交时间：2020/10/26 divertor and confinement  radiative power exhaust  scrape-off layer and divertor physics  steady state operation and transient heat loads  plasma facing components materials and heat exhaust for steady state operation  divertors for DEMO and reactors   Realization of ODS-Cu/T91 Tube-to-tube Joining with Rotary Friction Welding 期刊论文  OAI收割 FUSION ENGINEERING AND DESIGN, 2020, 卷号: 158 作者:  Zhao, Sixiang;  Wang, Minjing;  Kou, Shengzhong;  Jia, Zhi;  Wang, Wanjing   |  收藏  |  浏览/下载：58/0  |  提交时间：2020/11/30 Rotary friction welding  Rotary bending fatigue  Brittleness  ODS-Cu, T91   Impact of neutron irradiation on the strength and ductility of pure and ZrC reinforced tungsten grades 期刊论文  OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 537 作者:  Yin, Chao;  Terentyev, Dmitry;  Zhang, Tao;  Petrov, Roumen H.;  Pardoen, Thomas   |  收藏  |  浏览/下载：13/0  |  提交时间：2020/10/26 Molecular dynamics simulation of the diffusion of self-interstitial atoms and interstitial loops under temperature gradient field in tungsten 期刊论文  OAI收割 JOURNAL OF APPLIED PHYSICS, 2020, 卷号: 128, 期号: 6, 页码: 8 作者:  Fang, Jingzhong;  Liu, Lixia;  Gao, Ning;  Hu, Wangyu;  Gao, Fei   |  收藏  |  浏览/下载：9/0  |  提交时间：2021/12/15 A new method for improving the tritium breeding and releasing performance of China Fusion Engineering Test Reactor phase II helium-cooled ceramic breeder blanket 期刊论文  OAI收割 INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2020, 卷号: 44 作者:  Cui, Shijie;  Zhang, Dalin;  Lang, Yueheng;  Jiang, Xinyu;  Tian, Wenxi   |  收藏  |  浏览/下载：17/0  |  提交时间：2020/11/26 CFETR phase II  coupling optimization  dynamic feedback  HCCB blanket  high fusion power   Conceptual Design of 15 Tesla Conductor Test Facility for Future Fusion Reactor 期刊论文  OAI收割 IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2020, 卷号: 30 作者:  Dai, Chao;  Wu, Yu;  Qin, Jinggang;  Shi, Yi;  Xu, Aihua   |  收藏  |  浏览/下载：46/0  |  提交时间：2020/11/26 Conductors  Niobium-tin  Superconducting magnets  Magnetic fields  Magnetomechanical effects  Test facilities  Strain  CFETR  conductor test facility  split magnet  electro-magnetic design  conductor design   Development and experiments of LiPb coolant technologies for fusion blanket in China 期刊论文  OAI收割 INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2020 作者:  Huang, Qunying;  Zhu, Zhiqiang   |  收藏  |  浏览/下载：14/0  |  提交时间：2020/11/26 corrosion  DRAGON loops  LiPb blanket  LOCA  MHD   Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors 期刊论文  OAI收割 NUCLEAR FUSION, 2020, 卷号: 60 作者:  Liu, Xiaogang;  Wu, Fan;  Wang, Zhaoliang;  Li, Guoqiang;  Liu, Xiaoju   |  收藏  |  浏览/下载：29/0  |  提交时间：2020/11/26 tokamak  DEMO  superconducting magnet  TF  cable-in-conduit conductor  electromagnetic load  mechanical analysis