Study on Impact Buckling Simulation Analysis Method and Buckling Behavior of Fuel Assembly Spacer Grid

Liu Sheng; Li Pengzhou; Yang Yiren

doi:10.13832/j.jnpe.2024.03.0161

Volume 45 Issue 3

Jun. 2024

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Liu Sheng, Li Pengzhou, Yang Yiren. Study on Impact Buckling Simulation Analysis Method and Buckling Behavior of Fuel Assembly Spacer Grid[J]. Nuclear Power Engineering, 2024, 45(3): 161-169. doi: 10.13832/j.jnpe.2024.03.0161

Citation:

Liu Sheng, Li Pengzhou, Yang Yiren. Study on Impact Buckling Simulation Analysis Method and Buckling Behavior of Fuel Assembly Spacer Grid[J]. Nuclear Power Engineering, 2024, 45(3): 161-169. doi: 10.13832/j.jnpe.2024.03.0161

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Study on Impact Buckling Simulation Analysis Method and Buckling Behavior of Fuel Assembly Spacer Grid

doi: 10.13832/j.jnpe.2024.03.0161

1.
Nuclear Power Institute of China, Chengdu, 610213, China
2.
School of Mechanics and Aerospace Engineering, Southwest Jiaotong University, Chengdu, 610031, China

Received Date: 2023-09-11
Rev Recd Date: 2024-03-24
Publish Date: 2024-06-13

Abstract

Abstract

The fuel assembly spacer grid is a key part of the nuclear reactor and its dynamic buckling behaviors are important to the reactor structural safety. In this paper, the repeated impact simulation analysis method is established for the fuel assembly spacer grid, the differences between the simulation results of single impact and repeated impact and the test results are compared, and the influence of the simulation analysis method on the dynamic buckling behavior of grid impact is discussed. It is found that the simulation analysis method of repeated impact can simulate the cumulative deformation process of repeated impact in the test, and its simulation results are in better agreement with the test results. The impact force-initial velocity curves of the repeated impact simulation and the test form a yield platform near the buckling point, and the rebound coefficient and impact dynamic stiffness in the yield platform remain stable. After the yield platform, the impact force rapidly decreases, while the rebound velocity and rebound coefficient undergo drastic changes. However, the impact force and rebound velocity of the single simple impact simulation remain stable and slowly increase after the buckling point. Before buckling, the time history curve of the impact acceleration is approximately symmetrical; as the initial velocity increases, the rebound stage of the acceleration curve tails and makes its symmetry destroyed. The buckling deformation of the grids in the repeated impact simulation and the test is a first-order buckling failure dominated by transverse shear deformation at the bottom, while the buckling shape cannot be accurately predicted by the single simple impact simulation. The repeated impact simulation analysis method proposed in this paper can establish a more accurate analysis model and reveal the dynamic mechanical behavior in the buckling test of spacer grid more accurately.
- Spacer grid,
- Impact buckling,
- Repeat-impact,
- Impact force,
- Rebound coefficient,
- Impact stiffness

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References(14)

References

[1]	SONG K N, YOON K H. Nonlinear FE analysis on the static buckling behavior of the spacer grid structures[C]. Taejon, Korea: Proceedings of the Korean Nuclear Society Autumn Meeting, 2000.
[2]	YOO Y G, PARK N G, KIM K G, et al. Static buckling analysis of the partial spacer grid of the nuclear fuel assembly[C]. Nürnberg, Germany: Proceedings of ANSYS Conference and 32nd CADFEM Users’ Meeting, 2014.
[3]	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. doi: 10.3969/j.issn.0258-0918.2015.03.005
[4]	SUN J Y, DANG Y, LIU S, et al. Investigation into the influence of fuel rods on the anti-seismic mechanical characteristics of fuel assembly spacer grid by FEM method[C]//25th International Conference on Nuclear Engineering. Shanghai, China: ASME, 2017.
[5]	秦勉,蒲曾坪,陈平,等. 定位格架静态屈曲载荷分析方法研究[J]. 核动力工程,2018, 39(S1): 28-33.
[6]	YOON K H, KANG H S, KIM H K, et al. Nonlinear dynamic buckling behavior of a partial spacer grid assembly[J]. Journal of the Korean Nuclear Society, 2001, 33(1): 93-101.
[7]	YOON K H, HEO S P, SONG K N, et al. Dynamic impact analysis of the grid structure using multi-point constraint (MPC) equation under the lateral impact load[J]. Computers & Structures, 2004, 82(23-26): 2221-2228.
[8]	YOO Y, KIM K, EOM K, et al. Finite element analysis of the mechanical behavior of a nuclear fuel assembly spacer grid[J]. Nuclear Engineering and Design, 2019, 352: 110179. doi: 10.1016/j.nucengdes.2019.110179
[9]	ZHAO W, KAROUTAS Z, EVANS P, et al. LS-DYNA^® applications in simulating impact tests of nuclear fuel spacer grids and drop tests of fuel shipping packages[C]. Detroit, USA: 12th International LS-DYNA^® User Conference, 2012.
[10]	RYU J Y, WOO H G, PARK N G, et al. Spacer grid lateral crush strength depending on welding methods[C]. Jeju, Korea: Transactions of the Korean Nuclear Society Spring Meeting, 2019.
[11]	JEON S Y, LEE Y S. An estimation of the dynamic buckling load for the spacer grid of pressurized water reactor fuel assembly[J]. Key Engineering Materials, 2006, 326-328: 1603-1606. doi: 10.4028/www.scientific.net/KEM.326-328.1603
[12]	LIU S, FAN C G, YANG Y R. An impact test system design and its applications to dynamic buckling of a spacer grid assembly[J]. Nuclear Engineering and Design, 2016, 308: 252-260. doi: 10.1016/j.nucengdes.2016.08.027
[13]	郭严,张玉相. 压水堆燃料组件结构搅混格架动态屈曲仿真研究[J]. 核科学与工程,2018, 38(4): 533-539. doi: 10.3969/j.issn.0258-0918.2018.04.001
[14]	YOON K H, OH H R, KIM J Y, et al. Dynamic buckling behavior of cell setting & normal non-irradiated spacer grid using pendulum type impact test[C]. Yeosu, Korea: Transactions of the Korean Nuclear Society Autumn Meeting, 2018.