机构

• 合肥物质科学研究院 [18]
• 高能物理研究所 [4]
• 自动化研究所 [3]
• 宁波材料技术与工程研... [2]
• 近代物理研究所 [2]
• 长春光学精密机械与物... [1]
• 更多

采集方式

• OAI收割 [30]

内容类型

• 期刊论文 [23]
• 会议论文 [6]
• 学位论文 [1]

发表日期

• 2021 [30]

学科主题

• 计算机科学技术::人... [1]

筛选

浏览/检索结果: 共30条，第1-10条 帮助 限定条件 发表日期：2021     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 Effect of tungsten armor on electromagnetic characteristics of blanket for the fusion device under plasma disruption 期刊论文  OAI收割 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：46/0  |  提交时间：2021/11/01 Fusion device  First wall  Plasma disruption  Tungsten armor  Eddy current   First steps of the overall integration design of CFETR 期刊论文  OAI收割 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 173 作者:  Lu, Kun;  Song, Yuntao;  Cai, Lijun;  Peng, Xuebing;  Shen, Junsong   |  收藏  |  浏览/下载：30/0  |  提交时间：2022/01/10 CFETR  Integration design  Interface  Consistency   Accelerator Production of the Medical Isotope At-211 and Monoclonal Antibody Labeling 期刊论文  OAI收割 ACTA CHIMICA SINICA, 2021, 卷号: 79, 期号: 11, 页码: 1376-1384 作者:  Chen, Desheng;  Liu, Weihao;  Huang, Qinggang;  Cao, Shiwei;  Tian, Wei   |  收藏  |  浏览/下载：37/0  |  提交时间：2022/01/07 accelerator  medical isotope  dry distillation method  At-211  labeling   Optimization of helicon wave off-axis current drive in CFETR tokamak 期刊论文  OAI收割 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 172 作者:  Li, Xinxia;  Li, Guozhuang;  Liu, Hongbo   |  收藏  |  浏览/下载：27/0  |  提交时间：2021/11/15 Tokamak  CFETR  Helicon wave  Plasma current drive   Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW 期刊论文  OAI收割 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2021, 卷号: 49 作者:  Li, Jie;  Zhang, Jie;  Liu, Changle;  Liu, Xiaogang;  Gao, Xiang   |  收藏  |  浏览/下载：56/0  |  提交时间：2021/11/15 Neutrons  Plasmas  Solid modeling  Inductors  Production  Optimization  Loading  China Fusion Engineering Test Reactor (CFETR)  neutronics study  neutron wall loading (NWL)  tritium breeding ratio (TBR)  water-cooled ceramic breeder (WCCB)   Superconductors for fusion: a roadmap 期刊论文  OAI收割 SUPERCONDUCTOR SCIENCE & TECHNOLOGY, 2021, 卷号: 34 作者:  Mitchell, Neil;  Zheng, Jinxing;  Vorpahl, Christian;  Corato, Valentina;  Sanabria, Charlie   |  收藏  |  浏览/下载：33/0  |  提交时间：2021/11/01 fusion  superconductors  fusion power  superconductor technology  superconducting materials  superconducting magnets  energy   Development of TWA mock-up for TITAN 期刊论文  OAI收割 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 171 作者:  Li, Jiahao;  Ragona, R.;  Song, Yuntao;  Yang, Qingxi;  Yu, Chao   |  收藏  |  浏览/下载：38/0  |  提交时间：2021/11/01 TWA  ICRH  RF analysis  Structure analysis  assembly  WEST   Simulation of DNB-type critical heat flux (CHF) and pressure drop in subcooled flow boiling of water for tubes with twisted tape inserts under one-sided heating conditions 期刊论文  OAI收割 FUSION ENGINEERING AND DESIGN, 2021, 卷号: 170 作者:  Liu, P.;  Wang, P. T.;  Guo, Y. S.;  Tang, M. Y.;  Song, Y. T.   |  收藏  |  浏览/下载：37/0  |  提交时间：2021/11/01 Departure from nucleate boiling  Critical heat flux  Twisted tape inserts  Pressure drop  One-sided heating  Subcooled boiling   Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2 期刊论文  OAI收割 NUCLEAR MATERIALS AND ENERGY, 2021, 卷号: 28 作者:  Lu, Yudong;  Ye, Minyou;  Zhou, Guangming;  Hernandez, Francisco A.;  Leppanen, Jaakko   |  收藏  |  浏览/下载：38/0  |  提交时间：2021/11/01 Water cooled Lead Ceramic Breeder  Neutronics  Tritium breeding  Serpent-2   Modelling of the complete heat flux deposition on the CFETR first wall with neon seeding 期刊论文  OAI收割 Plasma Physics and Controlled Fusion, 2021, 卷号: 63 作者:  Nian,Feifei;  Yang,Zhongshi;  Ding,Rui;  Chen,Jingbo;  Niu,Guojian   |  收藏  |  浏览/下载：57/0  |  提交时间：2021/08/31 CFETR  complete heat flux  first wall  modelling  Ne seeding