Citation: | Jin Yuan, Zhou Sai, Chen Wei, Li Weicai, Zhang Yuxiang. Model Analysis of Fuel Assembly Grid Spring Stiffness[J]. Nuclear Power Engineering, 2024, 45(2): 154-159. doi: 10.13832/j.jnpe.2024.02.0154 |
[1] |
国家核安全局. 核动力厂设计安全规定: HAF 102-2016[S]. 北京: 环境保护部办公厅,2016: 6.
|
[2] |
IAEA. Review of fuel failures in water cooled reactors: IAEA Nuclear Energy Series No. NF-T-2.1[R]. Vienna: IAEA, 2010.
|
[3] |
杜光彦,张世权. 压水堆燃料组件方形定位格架结构设计、工艺特点和性能评价[J]. 核动力工程,1987, 8(3): 65-73.
|
[4] |
FERRARI G, KARAZIS K, AMABILI M. Experiments on the localized interaction at the interface fuel rod/spacer grid in pressurized water reactors[J]. Nuclear Engineering and Design, 2022, 399: 111998. doi: 10.1016/j.nucengdes.2022.111998
|
[5] |
任全耀,陈杰,赵瑞瑞,等. 新型定位格架夹持结构的力学特性研究[J]. 原子能科学计算,2020, 54(12): 2411-2417.
|
[6] |
蒋跃元,徐勇. NHR-200定位格架的设计研究[J]. 清华大学学报: 自然科学版,1996, 36(11): 6-11.
|
[7] |
王淅铖,王鼎渠,蒋跃元,等. NHR200-II燃料组件定位格架简化建模方法研究[J]. 核动力工程,2021, 42(4): 105-111.
|
[8] |
吴先洋,蒋跃元,王鼎渠,等. NHR200-II定位格架整体承载能力试验研究[J]. 核科学与工程,2015, 35(3): 424-433.
|
[9] |
蒋跃元,施继斌,徐勇. 供热堆格架力学性能试验研究[J]. 核动力工程,2007, 28(1): 22-25,31.
|
[10] |
SHIN M K, LEE H A, LEE J J, et al. Optimization of a nuclear fuel spacer grid spring using homology constraints[J]. Nuclear Engineering and Design, 2008, 238(10): 2624-2634. doi: 10.1016/j.nucengdes.2008.04.003
|
[11] |
KIM K S, YOON K H, SONG K N, et al. Finite element analysis of the optimized H type grid spring by using gap elements[J]. Nuclear Engineering and Design, 2008, 238(9): 2239-2244. doi: 10.1016/j.nucengdes.2008.02.025
|
[12] |
NEUPANE H, IBARRA L. Development of a spring model to predict the behavior of fuel rods in a spacer grid assembly[J]. Nuclear Engineering and Design, 2022, 394: 111826. doi: 10.1016/j.nucengdes.2022.111826
|