Author:
Shao Shihao,Liu Zhouyu,Xu Xiaobei,Zong Yufan,Cao Liangzhi,Wu Hongchun
Publisher
Springer Nature Singapore
Reference10 articles.
1. Hongchun W, Hongyi Y, Liangzhi C, et al. Current Status and Prospects of Key Analysis Software for Metal Cooled Fast Reactor[J]. Modern Applied Physics, 2021, 12(01): 4–15.
2. Feipeng Q. Development and Application of Performance Analysis Program for Liquid Metal Cooled Fast Reactor Fuel Elements[D]. University of Science and Technology of China, 2018.
3. Karahan A, Buongiorno J. Modeling of thermo-mechanical and irradiation behavior of mixed oxide fuel for sodium fast reactors[J]. Journal of Nuclear Materials, 2010, 396(2-3): 272–282.
4. Lainet M, Michel B, Dumas J C, et al. GERMINAL, a fuel performance code of the PLEIADES platform to simulate the in-pile behaviour of mixed oxide fuel pins for sodium-cooled fast reactors[J]. Journal of Nuclear Materials, 2019, 516: 30–53.
5. Tsuboi Y, Endo H, Ishizu T, et al. Analysis of fuel pin behavior under slow-ramp type transient overpower condition by using the fuel performance evaluation code ‘FEMAXI-FBR’[J]. Journal of Nuclear Materials, 2012, 49(4): 408–424.
Cited by
1 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献