Experimental Research of Bundle and Spacer Grid Arrangement on Fuel Assembly Mixing Characteristics

Cheng Cheng; Ye Tingpu; Lu Donghua; Su Qianhua; Long Biao; Chen Zhenhui

doi:10.13832/j.jnpe.2022.02.0022

Volume 43 Issue 2

Apr. 2022

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Cheng Cheng, Ye Tingpu, Lu Donghua, Su Qianhua, Long Biao, Chen Zhenhui. Experimental Research of Bundle and Spacer Grid Arrangement on Fuel Assembly Mixing Characteristics[J]. Nuclear Power Engineering, 2022, 43(2): 22-27. doi: 10.13832/j.jnpe.2022.02.0022

Citation:

Cheng Cheng, Ye Tingpu, Lu Donghua, Su Qianhua, Long Biao, Chen Zhenhui. Experimental Research of Bundle and Spacer Grid Arrangement on Fuel Assembly Mixing Characteristics[J]. Nuclear Power Engineering, 2022, 43(2): 22-27. doi: 10.13832/j.jnpe.2022.02.0022

Citation:

Cheng Cheng, Ye Tingpu, Lu Donghua, Su Qianhua, Long Biao, Chen Zhenhui. Experimental Research of Bundle and Spacer Grid Arrangement on Fuel Assembly Mixing Characteristics[J]. Nuclear Power Engineering, 2022, 43(2): 22-27. doi: 10.13832/j.jnpe.2022.02.0022

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Experimental Research of Bundle and Spacer Grid Arrangement on Fuel Assembly Mixing Characteristics

doi: 10.13832/j.jnpe.2022.02.0022

1.
Nuclear Power Technology Research Institute of China, Shenzhen, Guangdong, 518000, China
2.
School of Energy and Environment, Southeast University, Nanjing, 210096, China

Received Date: 2021-03-10
Rev Recd Date: 2021-04-30
Publish Date: 2022-04-02

Abstract

Abstract

Taking the 5×5 bundle fuel assembly assembled with the spacer grid used in CPR1000 nuclear power unit as the object, experiments on the mixing characteristics of several groups of full-length bundle fuel assembly were carried out. The effects of geometric parameters such as cold-hot rod arrangement and spacer grid arrangement on the mixing characteristics of fuel assembly are analyzed emphatically. The experimental results show that the thermal diffusion coefficient of the fuel assembly is closer to the true value when the cold-hot rods are symmetrically arranged in the center; The inter-span mixing spacer grid has a small enhancement effect on the overall thermal diffusion coefficient of fuel assembly, but its contribution to the pressure drop of bundle is very low.
- Fuel assembly,
- 5×5 bundle,
- Thermal diffusion coefficient,
- Geometrical parameters

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References(8)

References

[1]	曹念,郎雪梅,卢冬华,等. 燃料组件单相交混系数试验研究[J]. 核动力工程,2009, 30(5): 22-25, 47.
[2]	谢峰,曹念,郎雪梅,等. 紧密排列燃料组件交混系数试验研究[J]. 核动力工程,2012, 33(S1): 50-53, 58.
[3]	陈畏葓,张虹,张凤林,等. 先进燃料组件格架交混性能分析[J]. 核动力工程,2008, 29(3): 1-4, 27.
[4]	于平安, 朱瑞安, 喻真烷. 核反应堆热工分析[M]. 北京: 原子能出版社, 1986.
[5]	RAYMOND P, SPINDLER B, LENAIN R. Pressurized water reactor thermal-hydraulic core analysis with the FLICA computer code[J]. Nuclear Engineering and Design, 1990, 124(3): 299-313. doi: 10.1016/0029-5493(90)90298-C
[6]	刘余,杜思佳,李仲春. 子通道分析中的湍流交混研究综述[J]. 核动力工程,2017, 38(3): 132-136.
[7]	CARLUCCI L N, HAMMOUDA N, ROWE D S. Two-phase turbulent mixing and buoyancy drift in rod bundles[J]. Nuclear Engineering and Design, 2004, 227(1): 65-84. doi: 10.1016/j.nucengdes.2003.08.003
[8]	韩斌,杨保文,张汇,等. 定位格架压降关系式及CFD数值模拟研究[J]. 核动力工程,2017, 38(2): 169-174.