Research on Fatigue Performance of Newly Developed Supporting Structure of Spacer Grid

Guo Xiaoming; Ren Quanyao; Chen Jie; Ren Yi

doi:10.13832/j.jnpe.2023.04.0095

Volume 44 Issue 4

Aug. 2023

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Guo Xiaoming, Ren Quanyao, Chen Jie, Ren Yi. Research on Fatigue Performance of Newly Developed Supporting Structure of Spacer Grid[J]. Nuclear Power Engineering, 2023, 44(4): 95-99. doi: 10.13832/j.jnpe.2023.04.0095

Citation:

Guo Xiaoming, Ren Quanyao, Chen Jie, Ren Yi. Research on Fatigue Performance of Newly Developed Supporting Structure of Spacer Grid[J]. Nuclear Power Engineering, 2023, 44(4): 95-99. doi: 10.13832/j.jnpe.2023.04.0095

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Research on Fatigue Performance of Newly Developed Supporting Structure of Spacer Grid

doi: 10.13832/j.jnpe.2023.04.0095

1.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
2.
CNNC Jianzhong Nuclear Fuel Co., Ltd., Yibin, Sichuan, 644000, China

Received Date: 2022-09-29
Rev Recd Date: 2022-12-21
Publish Date: 2023-08-15

Abstract

Abstract

Aiming at the innovative supporting structure and its fatigue performance, this paper evaluates the stress state under its operating conditions by means of finite element analysis, and carries out the spring fatigue test to analyze the fatigue failure characteristics and crack initiation locations. The results show that the spring fatigue failure of the supporting structure roughly goes through the stages of load reduction and rapid failure. Due to the support legs of the spring, the spring still maintains a certain load after failure, which is about 0.42 times of the nominal load. The fatigue and crack locations are not only determined by the stress value, but also by the transferring feature of load. The finite element model is an effective method for the design and optimization of the supporting structure of spacer grid, and can preliminarily identify the location of fatigue failure.
- Spacer grid,
- Supporting structure,
- Fatigue performance,
- Spring

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References(15)

References

[1]	LIU C C, FERNG Y M. Numerically simulating the thermal-hydraulic characteristics within the fuel rod bundle using CFD methodology[J]. Nuclear Engineering and Design, 2010, 240(10): 3078-3086. doi: 10.1016/j.nucengdes.2010.05.021
[2]	CHEN D Q, XIAO Y, XIE S J, et al. Thermal-hydraulic performance of a 5×5 rod bundle with spacer grid in a nuclear reactor[J]. Applied Thermal Engineering, 2016, 103: 1416-1426. doi: 10.1016/j.applthermaleng.2016.05.028
[3]	KIM K T. A study on the grid-to-rod fretting wear-induced fuel failure observed in the 16×16KOFA fuel[J]. Nuclear Engineering and Design, 2010, 240(4): 756-762. doi: 10.1016/j.nucengdes.2009.12.014
[4]	SCHETTINO C F M, GOUVÊA J P, MEDEIROS N. Analyses of spacer grids compression strength and fuel assemblies structural behavior[J]. Nuclear Engineering and Design, 2013, 260: 93-103. doi: 10.1016/j.nucengdes.2013.03.008
[5]	REN Q Y, PAN L M, ZHOU W X, et al. Phase distribution characteristics of bubbly flow in 5×5 vertical rod bundles with mixing vane spacer grids[J]. Experimental Thermal and Fluid Science, 2018, 96: 451-459. doi: 10.1016/j.expthermflusci.2018.04.002
[6]	REN Q Y, PAN L M, ZHOU W X, et al. Drift-flux model of sub-channel in vertical rod bundles with spacer grids[J]. International Journal of Heat and Mass Transfer, 2018, 126: 946-956. doi: 10.1016/j.ijheatmasstransfer.2018.05.135
[7]	宋基男, 尹庆镐, 宋根禹, 等. 用于增大与燃料棒的共形接触面积的定位格架弹簧: 中国, 101055775A[P]. 2007-10-17.
[8]	严景保, 金圭泰, 徐正旻, 等. 具有防止燃料棒摩擦腐蚀的划艇形弹簧的支撑格架: 中国, 101377964A[P]. 2009-03-04.
[9]	YOON K H, LEE K H, KANG H S, et al. Analysis of the optimized H type grid spring by a characterization test and the finite element method under the in-grid boundary condition[J]. Nuclear Engineering and Technology, 2006, 38(4): 375-382.
[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]	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]. 原子能科学技术,2020, 54(12): 2411-2417. doi: 10.7538/yzk.2019.youxian.0943
[12]	肖林,白菊丽. 锆-4的反复弯曲高周疲劳性能及其显微组织[J]. 核科学与工程,1999, 19(2): 147-151.
[13]	田锋,李中奎,张建军,等. M5合金的高温低周疲劳性能研究[J]. 稀有金属,2008, 32(6): 694-697. doi: 10.3969/j.issn.0258-7076.2008.06.004
[14]	肖林,顾海澄. 锆及锆合金的疲劳行为及其变形机理[J]. 稀有金属材料与工程,1998, 27(2): 69-74. doi: 10.3321/j.issn:1002-185X.1998.02.002
[15]	秦勉, 蒲曾坪, 茹俊, 等. 单金属定位格架夹持结构性能分析方法研究[J]. 中国核电, 2016, 9(S1): 187-191.