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Neutronics design optimization of a small modular fast reactor based on response surface methodology 期刊论文
Nuclear Engineering and Design, 2022, 卷号: 395
作者:  Gao, Yucui;  Cao, Liangzhi;  Ye, Wenlian;  Yan, Xuesong;  Chen, Liangwen
收藏  |  浏览/下载:26/0  |  提交时间:2022/08/09
A kinetic rate theory modelling of fission gas release and fuel swelling for UN fuels 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2021, 卷号: 556, 页码: 14
作者:  Qian, Zhengyu;  Liu, Wenbo;  Yu, Rui;  Tao, Yujie;  Yun, Di
收藏  |  浏览/下载:36/0  |  提交时间:2021/12/08
Lead-Cooled Fast Reactor Annular UN Fuel Design and Development of Performance Analysis Program 期刊论文
FRONTIERS IN ENERGY RESEARCH, 2021, 卷号: 9, 页码: 9
作者:  Yuan, He;  Wang, Guan;  Yu, Rui;  Tao, Yujie;  Wang, Zhaohao
收藏  |  浏览/下载:15/0  |  提交时间:2021/12/08
Preliminary transient thermal-hydraulic analysis for new coated UN and UC fuel options in SCWR 期刊论文
PROGRESS IN NUCLEAR ENERGY, 2014, 卷号: 71, 期号: [db:dc_citation_issue], 页码: 152-159
作者:  Zhao, Hao;  Zhu, Dahuan;  Chaudri, Khurrum Saleem;  Qiu, Suizheng;  Tian, Wenxi
收藏  |  浏览/下载:7/0  |  提交时间:2019/12/02


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