机构

• 合肥物质科学研究院 [12]
• 工程热物理研究所 [2]
• 力学研究所 [1]
• 近代物理研究所 [1]

采集方式

• OAI收割 [16]

内容类型

• 期刊论文 [16]

发表日期

• 2021 [3]
• 2020 [3]
• 2019 [1]
• 2018 [3]
• 2017 [1]
• 2016 [2]
• 更多

学科主题

筛选

浏览/检索结果: 共16条，第1-10条 帮助 条数/页： 5101520253035404550556065707580859095100 排序方式： 请选择题名升序题名降序提交时间升序提交时间降序作者升序作者降序发表日期升序发表日期降序 Scoping study of lower hybrid current drive for CFETR 期刊论文  OAI收割 NUCLEAR FUSION, 2021, 卷号: 61 作者:  Wallace, G. M.;  Din, B. J.;  Li, M. H.;  Chen, J.;  Baek, S. G.   |  收藏  |  浏览/下载：42/0  |  提交时间：2021/11/01 lower hybrid current drive  china fusion engineering test reactor  non-inductive current drive  steady state tokamak   Integrated modeling of CFETR hybrid scenario plasmas 期刊论文  OAI收割 NUCLEAR FUSION, 2021, 卷号: 61 作者:  Chen, Jiale;  Chan, Vincent S.;  Jian, Xiang;  Zhang, Xinjun;  Ren, Qilong   |  收藏  |  浏览/下载：35/0  |  提交时间：2021/04/26 integrated modeling  CFETR  hybrid scenario for tokamak fusion reactor  turbulent transport  heating and current drive  particle transport   Recent Progress in Modeling of CFETR Plasma Profiles from Core to Edge 期刊论文  OAI收割 JOURNAL OF FUSION ENERGY, 2021, 卷号: 40 作者:  Chen, Jiale;  Jia, Guozhang;  Xiang, Nong   |  收藏  |  浏览/下载：36/0  |  提交时间：2021/05/10 CFETR  Integrated modeling  Scenario development  Coupling between core and edge  Tokamak reactor   Strategy Study and Preliminary Conceptual Design of the Remote Maintenance Systems for in Vessel Components of CFETR 期刊论文  OAI收割 JOURNAL OF FUSION ENERGY, 2020 作者:  Zhao, Wenlong;  Shi, Shanshuang;  Cheng, Yong;  Huang, Jianjun;  Sun, Huibin   |  收藏  |  浏览/下载：38/0  |  提交时间：2020/11/26 CFETR  Fusion reactor  Remote maintenance  Tokamak design  Compatibility   CFETR α粒子在纵场波纹扰动下的损失模拟 期刊论文  OAI收割 中国科学. 物理学, 力学, 天文学, 2020, 卷号: 50 作者:  郝保龙;  陈伟;  蔡辉山;  李国强;  王丰   |  收藏  |  浏览/下载：33/0  |  提交时间：2020/11/25 fusion reactor  tokamak  α particle  toroidal field ripple  聚变堆  托卡马克  α粒子  纵场波纹   Discharge simulation and volt-second consumption analysis during ramp-up on the CFETR tokamak 期刊论文  OAI收割 CHINESE PHYSICS B, 2020, 卷号: 29 作者:  Liu, Cheng-Yue;  Wu, Bin;  Qian, Jin-Ping;  Li, Guo-Qiang;  Hou, Ya-Wei   |  收藏  |  浏览/下载：87/0  |  提交时间：2020/11/26 plasma current ramp-up  China Fusion Engineering Test Reactor  tokamak simulation code  volt-second consumption   Present State of Chinese Magnetic Fusion Development and Future Plans 期刊论文  OAI收割 JOURNAL OF FUSION ENERGY, 2019, 卷号: 38, 期号: 1, 页码: 113-124 作者:  Li, Jiangang;  Wan, Yuanxi   |  收藏  |  浏览/下载：25/0  |  提交时间：2020/03/31 Fusion  Tokamak  Reactor   The Feasibility of Application of the Existing IVVS Concept to CFETR 期刊论文  OAI收割 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 6, 页码: 2203-2206 作者:  Zhou, Zibo;  Cao, Lei;  Xu, Houchang;  Yao, Damao   |  收藏  |  浏览/下载：26/0  |  提交时间：2019/11/12 Chinese Fusion Engineering Test Reactor (CFETR)  cylindrical vessel  Experimental Advanced Superconducting Tokamak (EAST)  in-vessel viewing system (IVVS)   Tokamak Design and Maintenance Scheme Tradeoff Application on CFETR 期刊论文  OAI收割 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1156-1165 作者:  Villedieu, E.;  Song, Y. T.;  Cheng, Y.;  Zhan, J.;  Dechelle, C.   |  收藏  |  浏览/下载：31/0  |  提交时间：2019/08/23 Fusion reactor design  maintenance  remote handling  tokamak   Progress of Concept Design for CFETR Diagnostic System 期刊论文  OAI收割 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1361-1365 作者:  Yang, Yao;  Li, Gongshun;  Wang, Yumin;  Ming, Tingfeng;  Han, Xiang   |  收藏  |  浏览/下载：30/0  |  提交时间：2019/08/23 Chinese fusion engineering test reactor (CFETR)  diagnostic system  tokamak