中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
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浏览/检索结果: 共24条,第1-10条 帮助

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Analysis of zirconium hydride moderator effect on the micro lead-based reactor 期刊论文  OAI收割
ANNALS OF NUCLEAR ENERGY, 2025, 卷号: 210
作者:  
Sun, Yanting;  Zou, Xiaoliang;  Qin, Zhijie;  Zhang, Shichao
  |  收藏  |  浏览/下载:3/0  |  提交时间:2024/11/20
An improved analysis method for assessing the nuclear-heating impact on the stability of toroidal field magnets in fusion reactors 期刊论文  OAI收割
NUCLEAR SCIENCE AND TECHNIQUES, 2024, 卷号: 35
作者:  
Lu, Yu-Dong;  Zheng, Jin-Xing;  Liu, Xu-Feng;  Wu, Huan;  Ge, Jian
  |  收藏  |  浏览/下载:3/0  |  提交时间:2024/11/20
Neutronics assessments of LHCD antenna system for CFETR 期刊论文  OAI收割
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 172
作者:  
Wu, Qiuran;  Lu, Peng;  Zheng, Yu;  Du, Hua;  Liu, Liang
  |  收藏  |  浏览/下载:48/0  |  提交时间:2021/11/15
Neutronics analysis of a stacked structure for a subcritical system with LEU solution driven by a D-T neutron source for Mo-99 production 期刊论文  OAI收割
NUCLEAR SCIENCE AND TECHNIQUES, 2021, 卷号: 32
作者:  
Ren, Lei;  Han, Yun-Cheng;  Zhang, Jia-Chen;  Wang, Xiao-Yu;  Li, Tao-Sheng
  |  收藏  |  浏览/下载:41/0  |  提交时间:2022/01/10
Neutronics and shielding design of CFETR HCCB blanket 期刊论文  OAI收割
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 172
作者:  
Cao, Qixiang;  Wang, Xiaoyu;  Wu, Xinghua;  Yin, Miao;  Qu, Shen
  |  收藏  |  浏览/下载:41/0  |  提交时间:2022/01/10
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:71/0  |  提交时间:2021/11/15
Activation and radwaste analysis for ITER soft X-ray camera 期刊论文  OAI收割
FUSION ENGINEERING AND DESIGN, 2021, 卷号: 171
作者:  
Huang, Liangsheng;  Niu, Luying;  Chen, Kaiyun;  Zhang, Xiaokang;  Hu, Liqun
  |  收藏  |  浏览/下载:30/0  |  提交时间:2021/11/29
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:58/0  |  提交时间:2021/11/01
Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D-T neutron irradiation conditions 期刊论文  OAI收割
NUCLEAR FUSION, 2021, 卷号: 61
作者:  
Zhu, Qingjun;  Chen, Wuhui;  Bao, Jie;  Du, Hua;  Liu, Songlin
  |  收藏  |  浏览/下载:41/0  |  提交时间:2021/06/15
Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D–T neutron irradiation conditions 期刊论文  OAI收割
Nuclear Fusion, 2021, 卷号: 61
作者:  
Zhu,Qingjun;  Chen,Wuhui;  Bao,Jie;  Du,Hua;  Liu,Songlin
  |  收藏  |  浏览/下载:28/0  |  提交时间:2021/06/21