Conjugate Heat Transfer Numerical Analysis of Guide Tube of Sodium-cooled Fast Reactor Hydraulic Suspended Passive Shutdown Mechanism

被引：0
|
作者：
Ren Y. [1 ]
Yu H. [1 ]
机构：
[1] China Institute of Atomic Energy, Beijing
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2020年 / 54卷 / 04期
关键词：
Conjugate heat transfer; Guide tube; Hexahedral mesh; OpenFOAM; Sodium-cooled fast reactor;
D O I：
10.7538/yzk.2019.youxian.0316
中图分类号：
学科分类号：
摘要：
In order to solve the conjugate heat transfer problem formed by the guide tube of sodium-cooled fast reactor hydraulic suspended passive shutdown mechanism and the liquid sodium on its inner and outer sides, Trelis, a pre-processing software was used to generate the global high-quality hexahedral mesh, and a solver called chtMultiRegionSimpleFoam of OpenFOAM, which is an open source CFD software, was applied. The temperature distribution results of the numerical analysis of the guide tube were obtained. The results show that the temperature difference in the range of 0.07 m in the circumferential direction of the inner wall of the guide tube is 97℃, and the temperature difference in the range of 0.17 m in the axial direction is 80℃. In such a narrow range, the temperature difference will generate large thermal stress, and the numerical analysis results of which will provide an important input for the mechanical design of the guide tube. © 2020, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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页码：615 / 623
页数：8
相关论文
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  • [1] Nuclear Technology Review 2018, (2018)
  • [2] Wang P., Zhu J., LOF accident analysis for a sodium-cooled FBR, Chinese Journal of Nuclear Science and Engineering, 16, 2, pp. 180-184, (1996)
  • [3] Hu W., Ren L., Li Z., Et al., Study on technical scheme for passive shutdown of pool-type sodium-cooled fast reactor, Nuclear Science and Engineering, 34, 1, pp. 23-27, (2014)
  • [4] Tinoco H., Lindqvist H., Thermal mixing instability of the flow inside a control rod guide tube, (2009)
  • [5] Ignacio G., Thermal mixing CHT simulations with OpenFOAM: URANS and LES, (2013)
  • [6] Koloszar L., Buckingham S., Planquart P., Et al., MyrrhaFoam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA, Nuclear Engineering and Design, 312, pp. 256-265, (2017)
  • [7] Pini A., Cammi A., Cauzzi M., Et al., An Experimental facility to investigate the natural circulation dynamics in presence of distributed heat sources, Energy Procedia, 101, pp. 10-17, (2016)
  • [8] Yan C., Yu J., Xu J., Et al., On the achievements and prospects for the methods of computational fluid dynamics, Advances in Mechanics, 41, 5, pp. 572-577, (2011)
  • [9] Li S., Qi S., Ma X., Et al., Numerical simulation of CEFR fuel assembly pin flow distribution in flow 1 zone, Atomic Energy Science and Technology, 48, 2, pp. 251-256, (2014)
  • [10] Versteeg H.K., Malalasekera W., An Introduction to Computational Fluid Dynamics, pp. 75-77, (2007)
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