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浏览/检索结果: 共8条，第1-8条 帮助 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 The effect of blanket system and port plugs on the harmonic components of error field and optimizing approach investigation 期刊论文 NUCLEAR FUSION, 2023, 卷号: 63 作者:  Liu, Zhao;  Lei, Mingzhun;  Wu, Qigang;  Liu, Sumei 收藏  |  浏览/下载：8/0  |  提交时间：2023/11/17 CFETR  blanket system  error field  Fourier decomposition   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：43/0  |  提交时间：2022/01/10 Occupational radiation exposure  risk assessment  collective dose  fusion demonstration reactors   Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2 期刊论文 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：35/0  |  提交时间：2021/11/01 Water cooled Lead Ceramic Breeder  Neutronics  Tritium breeding  Serpent-2   Current Status and Progress on the Shielding Blanket of CFETR 期刊论文 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 5, 页码: 1417-1421 作者:  Liu, Changle;  Yang, Hao;  Zhang, Jie;  Zhang, Jianzhong;  Li, Lei 收藏  |  浏览/下载：9/0  |  提交时间：2019/08/23 Chinese fusion engineering test reactor (CFETR)  demonstration reactors (DEMO)  neutronics  shielding blanket (SB)   Experiment of joints resistance and critical current of Bi2212 conductor 期刊论文 FUSION ENGINEERING AND DESIGN, 2017, 卷号: 122, 页码: 228-231 作者:  Liu, Fang;  Liu, Huajun;  Qin, Jinggang;  Li, Jiangang;  Wu, Yu 收藏  |  浏览/下载：14/0  |  提交时间：2019/02/28 Bi2212 conductor  Transformer  Joint  Critical current   Manufacture and Test of Bi-2212 Cable-in-Conduit Conductor 期刊论文 IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2017, 卷号: 27, 期号: 4, 页码: 4801205 作者:  Qin, Jing-Gang;  Wu, Yu;  Li, Jian-Gang;  Dai, Chao;  Liu, Fang 收藏  |  浏览/下载：28/0  |  提交时间：2018/05/02 Bi2212  Conductor  Critical Current   Identification of safety gaps for fusion demonstration reactors 期刊论文 NATURE ENERGY, 2016, 卷号: 1, 期号: 无, 页码: 1-11 作者:  Wu, Y.;  Chen, Z.;  Hu, L.;  Jin, M.;  Li, Y. 收藏  |  浏览/下载：18/0  |  提交时间：2018/05/02 Preliminary thermal hydraulic safety analysis of water-cooled ceramic breeder blanket for CFETR 期刊论文 JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2016, 卷号: 53, 期号: 11, 页码: 1673-1680 作者:  Cheng, Xiaoman;  Ma, Xuebin;  Chen, Youhua;  Huang, Kai;  Liu, Songlin 收藏  |  浏览/下载：11/0  |  提交时间：2017/12/18 Cfetr  Blanket  Thermal Hydraulics  Accident Analysis  Relap5