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浏览/检索结果: 共10条，第1-10条 帮助 限定条件 发表日期：2020     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 R&D achievements for vacuum vessel towards CFETR construction 期刊论文 NUCLEAR FUSION, 2020, 卷号: 60 作者:  Liu, Zhihong;  Ji, Haibiao;  Wu, Jiefeng;  Wu, Huapeng;  Ma, Jianguo 收藏  |  浏览/下载：58/0  |  提交时间：2020/11/30 CFETR  vacuum vessel  sector  fabrication   Simulation studies of divertor power exhaust with neon seeding for CFETR with GW-level fusion power 期刊论文 PHYSICS OF PLASMAS, 2020, 卷号: 27 作者:  Liu, X. J.;  Xu, G. L.;  Ding, R.;  Jia, G. Z.;  Sang, C. F. 收藏  |  浏览/下载：24/0  |  提交时间：2020/11/30 Helicon wave damping coefficient of Chinese fusion engineering testing reactor plasma 期刊论文 ACTA PHYSICA SINICA, 2020, 卷号: 69 作者:  Li Xin-Xia;  Li Guo-Zhuang;  Liu Hong-Bo 收藏  |  浏览/下载：15/0  |  提交时间：2020/10/26 helicon wave  Chinese fusion engineering testing reactor  plasma dispersion function  electron landau damping   Scheduling Risk Evaluation for the Integrated Design of Blanket System Project for CFETR Based on Fuzzy PRET Method 期刊论文 JOURNAL OF FUSION ENERGY, 2020 作者:  Zhang, Ruonan;  Zhu, Yinfeng;  Xu, Shuling 收藏  |  浏览/下载：20/0  |  提交时间：2020/11/26 Schedule risk  PRET method  Integrated design  Blanket system  CFETR  Magnetic confinement   Preliminary Design Progress of the CFETR Water-Cooled Divertor 期刊论文 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48 作者:  Qin, Shijun;  Yao, Damao;  Wang, Qingfeng;  Mao, Xin;  Liu, Peng 收藏  |  浏览/下载：23/0  |  提交时间：2020/10/26 Cooling  Plasma temperature  Thermal analysis  Heating systems  Heat engines  Stress  Chinese Fusion Engineering and Testing Reactor (CFETR)  design and analysis  divertor  water-cooled   Development and Test Results of a Full-Size Joint Sample for the CFETR Central Solenoid Model Coil 期刊论文 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48 作者:  Ma, Guanghui;  Wu, Yu;  Qin, Jinggang;  Liu, Huajun;  Hao, Qiangwang 收藏  |  浏览/下载：84/0  |  提交时间：2020/10/26 Conductors  Welding  Cable shielding  Resistance  Steel  Soldering  Silver  Cable-in-conduit conductor (CICC)  central solenoid model coil (CSMC)  Chinese Fusion Engineering Testing Reactor (CFETR)  dc resistance  joint   Control and Diagnostic System for CFETR CSMC Testing Platform 期刊论文 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 卷号: 48 作者:  Li, Tong;  Liu, Huajun;  Wu, Yu;  Wang, Weijun;  Li, Fangyi 收藏  |  浏览/下载：61/0  |  提交时间：2020/10/26 Testing  Superconducting magnets  Protocols  Control systems  Alarm systems  Physics  Instruments  Central solenoid model coil (CSMC)  channel access (CA) protocol  Chinese fusion engineering testing reactor (CFETR)  control system  magnet diagnostic system (MDS)  magnet testing platform   Study on the dimensional metrology and alignment method for the 1/32 CFETR VV mock-up 期刊论文 FUSION ENGINEERING AND DESIGN, 2020, 卷号: 155 作者:  Gu, Yongqi;  Liu, Chen;  Wei, Jing;  Lu, Kun;  Ji, Haibiao 收藏  |  浏览/下载：17/0  |  提交时间：2020/11/26 CFETR VV  Inspection of the complex spatial surface  Assembly alignment  Best-fit  Reverse modeling  Machining alignment   Primary heat transfer system design of the WCCB blanket for multiple operation modes of CFETR 期刊论文 FUSION ENGINEERING AND DESIGN, 2020, 卷号: 153 作者:  Cheng, Xiaoman;  Ma, Xuebin;  Wang, Wenjia;  Chen, Lei;  Liu, Songlin 收藏  |  浏览/下载：13/0  |  提交时间：2020/11/26 CFETR  WCCB blanket  PHTS design   Progress of physics understanding for long pulse high-performance plasmas on EAST towards the steady-state operation of ITER and CFETR 期刊论文 PLASMA PHYSICS AND CONTROLLED FUSION, 2020, 卷号: 62 作者:  Huang, J.;  Gong, X.;  Garofalo, A. M.;  Qian, J.;  Chen, J. 收藏  |  浏览/下载：29/0  |  提交时间：2020/10/26 tokamak  steady state  long pulse  high bootstrap current