CFD Calculation and Analysis of Boiling Heat Transfer of Full-length Fuel Bundle with Bent Rod

被引:0
作者
Ren B. [1 ]
Gan F. [1 ]
Yang P. [1 ]
机构
[1] Shanghai Nuclear Engineering Research & Design Institute Co., Ltd., Shanghai
来源
Hedongli Gongcheng/Nuclear Power Engineering | 2022年 / 43卷 / 06期
关键词
Bending; Boiling; Computational fluid dynamics(CFD); Fuel bundle;
D O I
10.13832/j.jnpe.2022.06.0043
中图分类号
学科分类号
摘要
The boiling heat transfer in a 5 × 5 full-length fuel bundle containing a bent fuel rod is simulated by computational fluid dynamics (CFD) analysis. The calculation is based on the Eulerian-Eulerian two-fluid model and the improved wall boiling model, and the calculation method is verified based on the test data in the PSBT benchmark task. The calculated average void fraction of the cross section is in good agreement with the test data, which indicates the reliability of the existing calculation methods. Based on the calculation results, the effects of bent rod on the flow field, temperature field, void fraction and other key parameters in the bundle channel are investigated. The research results show that the existence of bent fuel rod has no significant impact on the cross section transverse flow, fluid temperature, void fraction, etc., but the increase of the surface temperature of bent fuel rod will also lead to bubble aggregation, which increases the risk of critical heat flux (CHF). © 2022 Yuan Zi Neng Chuban She. All rights reserved.
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页码:43 / 50
页数:7
相关论文
共 10 条
[1]  
38, pp. 25-28, (2017)
[2]  
40, 3, pp. 185-190, (2019)
[3]  
TOMIYAMA A, KATAOKA I, ZUN I, Et al., Drag coefficients of single bubbles under normal and micro gravity conditions, JSME International Journal Series B:Fluids and Thermal Engineering, 41, 2, pp. 472-479, (1998)
[4]  
BURNS A D, FRANK T, HAMILL I, Et al., The Favre averaged drag model for turbulent dispersion in Eulerian multi-phase flows, 5th International Conference on Multiphase Flow, (2004)
[5]  
KURUL N, PODOWSKI M Z., Multidimensional effects in forced convection subcooled boiling, International Heat Transfer Conference 9, (1990)
[6]  
COLE R., A photographic study of pool boiling in the region of the critical heat flux, AIChE Journal, 6, 4, pp. 533-538, (1960)
[7]  
KOCAMUSTAFAOGULLARI G, ISHII M., Foundation of the interfacial area transport equation and its closure relations, International Journal of Heat and Mass Transfer, 38, 3, pp. 481-493, (1995)
[8]  
HIBIKI T, ISHII M., Active nucleation site density in boiling systems, International Journal of Heat and Mass Transfer, 46, 14, pp. 2587-2601, (2003)
[9]  
DEL VALLE V H, KENNING D B R., Subcooled flow boiling at high heat flux, International Journal of Heat and Mass Transfer, 28, 10, pp. 1907-1920, (1985)
[10]  
RUBIN A, SCHOEDEL A, AVRAMOVA M., OECD/NRC benchmark based on NUPEC PWR Subchannel and Bundle Tests (PSBT). Volume I: experimental database and final problem specifications: NEA/NSC/DOC(2012)1, (2012)