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浏览/检索结果: 共118条，第1-10条 帮助 限定条件 发表日期：2021    专题：合肥物质科学研究院    第一署名单位    第一作者单位    通讯作者单位     已选(0)清除 条数/页：5101520253035404550556065707580859095100   排序方式：请选择作者升序作者降序题名升序题名降序发表日期升序发表日期降序提交时间升序提交时间降序 Efficient electrocatalytic nitrogen reduction to ammonia with aqueous silver nanodots 期刊论文 COMMUNICATIONS CHEMISTRY, 2021, 卷号: 4 作者:  Li, Wenyi;  Li, Ke;  Ye, Yixing;  Zhang, Shengbo;  Liu, Yanyan 收藏  |  浏览/下载：318/0  |  提交时间：2021/03/15 Occupational Radiation Exposure Estimated for Fusion Demonstration Reactors and Beyond 期刊论文 FUSION SCIENCE AND TECHNOLOGY, 2021 作者:  Guo, Dingqing;  Chen, Chao;  Wang, Zhen;  Lin, Jian;  Zhang, Bing 收藏  |  浏览/下载：44/0  |  提交时间：2022/01/10 Occupational radiation exposure  risk assessment  collective dose  fusion demonstration reactors   Design of Coordination System for Composite Mobile Robot Platform Oriented to Nuclear Fusion Vessel 期刊论文 JOURNAL OF FUSION ENERGY, 2021, 卷号: 40 作者:  Zhang, Qiang;  Song, Bo;  Cai, Bin;  Sun, Yuxiang 收藏  |  浏览/下载：53/0  |  提交时间：2021/11/16 EAST nuclear fusion reactor vessel  Multi-joint remote control system  Composite multi-joint remote operation robot platform  Bidirectional coordinated control  Load-bearing performance test   Conceptual design of the supercritical CO2 cooled lithium lead blanket for CFETR 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Chen, Lei;  Jiang, Kecheng;  Ma, Xuebin;  Wu, Qiuran;  Yu, Yi 收藏  |  浏览/下载：65/0  |  提交时间：2021/11/15 CFETR  Supercritical CO2 cooled lithium lead blanket  Performance analysis  Thermal efficiency evaluation   A study on nuclear analysis of the divertor region of the CFETR 期刊论文 PLASMA SCIENCE & TECHNOLOGY, 2021, 卷号: 23 作者:  Saidahmed, Rayyan;  Yao, Damao;  Wu, Qiuran;  Liu, Songlin;  Xu, Tiejun 收藏  |  浏览/下载：25/0  |  提交时间：2021/11/15 CFETR  fusion reactor  divertor  nuclear analysis  divertor region   Effect of tungsten armor on electromagnetic characteristics of blanket for the fusion device under plasma disruption 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Zhang, Shanwen;  Kong, Min;  Zhu, Lin;  Du, Shuangsong;  Feng, Changle 收藏  |  浏览/下载：47/0  |  提交时间：2021/11/01 Fusion device  First wall  Plasma disruption  Tungsten armor  Eddy current   Preliminary design of real-time plasma control system for CFETR 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Yuan, Q. P.;  Guo, H. R.;  Yan, L. L.;  Huang, Z. M.;  Huang, J. J. 收藏  |  浏览/下载：54/0  |  提交时间：2021/11/01 Real-time plasma control system  Control framework  PCS software development platform  PCS verification platform   Neutron characterization analysis of the negative ion-based neutral beam verification facility for CFETR 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Chen, Yuqing;  Wang, Ji;  Wu, Bin;  Yang, Zhen;  Li, Jun 收藏  |  浏览/下载：40/0  |  提交时间：2021/11/29 CFETR NNBVF  Neutron emission  Gaussian divergence   Study on electron beam welding process of the first wall of water-cooled ceramic breeder (WCCB) blanket 期刊论文 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Zhang, Yong;  Wu, Jiefeng;  Liu, Zhihong;  Liu, Songlin;  Lei, Mingzhun 收藏  |  浏览/下载：63/0  |  提交时间：2022/01/10 Electron beam welding  Blanket  First wall  Mechanical properties  Welding technology   Fabricating tritium permeation barrier for PFC with a new non-coating strategy 期刊论文 PHYSICA SCRIPTA, 2021, 卷号: 96 作者:  Wang, Lu;  Zhou, Hai-Shan;  Liu, Hao-Dong;  Xu, Yu-Ping;  Wang, Wan-Jing 收藏  |  浏览/下载：63/0  |  提交时间：2022/01/10 tritium permeation barrier  plasma-driven permeation  deuterium  hot isostatic pressing  aluminum oxidation