Numerical Analysis of Influence of Positioning and Wrapping Wire Structure on Thermohydraulic Characteristics of Rod Bundle Channel

Liu Sichao; Liu Yu; Tian Ruifeng; Yang Xiaolei; Chen Xi; Li Xiaochang

doi:10.13832/j.jnpe.2023.02.0037

Volume 44 Issue 2

Apr. 2023

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Liu Sichao, Liu Yu, Tian Ruifeng, Yang Xiaolei, Chen Xi, Li Xiaochang. Numerical Analysis of Influence of Positioning and Wrapping Wire Structure on Thermohydraulic Characteristics of Rod Bundle Channel[J]. Nuclear Power Engineering, 2023, 44(2): 37-42. doi: 10.13832/j.jnpe.2023.02.0037

Citation:

Liu Sichao, Liu Yu, Tian Ruifeng, Yang Xiaolei, Chen Xi, Li Xiaochang. Numerical Analysis of Influence of Positioning and Wrapping Wire Structure on Thermohydraulic Characteristics of Rod Bundle Channel[J]. Nuclear Power Engineering, 2023, 44(2): 37-42. doi: 10.13832/j.jnpe.2023.02.0037

Citation:

Liu Sichao, Liu Yu, Tian Ruifeng, Yang Xiaolei, Chen Xi, Li Xiaochang. Numerical Analysis of Influence of Positioning and Wrapping Wire Structure on Thermohydraulic Characteristics of Rod Bundle Channel[J]. Nuclear Power Engineering, 2023, 44(2): 37-42. doi: 10.13832/j.jnpe.2023.02.0037

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Numerical Analysis of Influence of Positioning and Wrapping Wire Structure on Thermohydraulic Characteristics of Rod Bundle Channel

doi: 10.13832/j.jnpe.2023.02.0037

1.
College of Nuclear Science and Technology, Harbin Engineering University, Harbin, 150001, China
2.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
3.
College of Aerospace and Civil Engineering, Harbin Engineering University, Harbin, 150001, China

Received Date: 2022-06-16
Rev Recd Date: 2022-08-21
Publish Date: 2023-04-15

Abstract

Abstract

The positioning and wrapping wire design is widely applied in the core design of metal cooled fast reactor and gas cooled fast reactor. In this paper, the effects of pitch, number and shape of positioning and wrapping wires on the flow and heat transfer of supercritical carbon dioxide in rod bundle channel are simulated and analyzed based on three-dimensional fine mesh model of wrapping wire positioning rod bundle channel. The simulation results show that positioning and wrapping wire pitch has a greater influence on the temperature field and flow field than the positioning and wrapping wire number and shape. When the positioning and wrapping wire pitch is less than 200 mm, pressure drop at the inlet and outlet increases significantly, surface heat transfer coefficient increases, and temperature non-uniformity decreases significantly and the temperature unevenness decreases greatly; with the increase in the number of the positioning and wrapping wires, pressure drop at the inlet and outlet increases linearly, but the surface heat transfer coefficient changes little; circular positioning and wrapping wire can achieve a similar effect to that of rectangular positioning and wrapping wire with a smaller cross-sectional area, and trapezoidal positioning and wrapping wire has less influence on flow field than rectangular positioning and wrapping wire.

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References(11)

References

[1]	ETER A, GROENEVELD D, TAVOULARIS S. An experimental investigation of supercritical heat transfer in a three-rod bundle equipped with wire-wrap and grid spacers and cooled by carbon dioxide[J]. Nuclear Engineering and Design, 2016, 303: 173-191. doi: 10.1016/j.nucengdes.2016.04.002
[2]	李明刚,聂常华,徐长哲. 四根绕丝定位19棒束组件流动传热特性[J]. 工业技术创新,2021, 8(1): 115-122. doi: 10.14103/j.issn.2095-8412.2021.01.019
[3]	臧金光,闫晓,黄善仿,等. 含绕丝2×2棒束内超临界水传热特性数值研究[J]. 核动力工程,2014, 35(2): 33-36.
[4]	WANG X A, ZHANG D L, WANG M J, et al. Generating hexahedral mesh for wire-wrapped fuel assembly with RBF mesh deformation method[J]. Frontiers in Energy Research, 2021, 8: 616890. doi: 10.3389/fenrg.2020.616890
[5]	丛腾龙,王俊杰,肖瑶,等. 铅铋冷却绕丝燃料组件横流特性分析[J]. 原子能科学技术,2022, 56(12): 2725-2734.
[6]	李虹锐,薛秀丽,周志伟. 绕丝棒束组件低流速时摩擦阻力实验研究[J]. 原子能科学技术,2021, 55(6): 1054-1059. doi: 10.7538/yzk.2020.youxian.0534
[7]	WANG S Q, WANG H, ZANG J G, et al. Numerical simulation of the thermal-hydraulic characteristics of supercritical carbon dioxide in a wire-wrapped rod bundle[J]. Applied Thermal Engineering, 2021, 198: 117443. doi: 10.1016/j.applthermaleng.2021.117443
[8]	MERZARI E, POINTER W D, SMITH J G, et al. Numerical simulation of the flow in wire-wrapped pin bundles: effect of pin-wire contact modeling[J]. Nuclear Engineering and Design, 2012, 253: 374-386. doi: 10.1016/j.nucengdes.2011.09.030
[9]	SHAMS A, ROELOFS F, BAGLIETTO E, et al. High fidelity numerical simulations of an infinite wire-wrapped fuel assembly[J]. Nuclear Engineering and Design, 2018, 335: 441-459. doi: 10.1016/j.nucengdes.2018.06.012
[10]	郜冶,李小畅. 压水堆四通道模型全高度上的单相流数值模拟[J]. 哈尔滨工程大学学报,2013, 34(3): 292-297.
[11]	王俊峰, 黄彦平. 一种超临界二氧化碳反应堆燃料组件: 中国, CN109273105B[P]. 2022-03-25.