Numerical Simulation Method of Boiling Heat Transfer and Its Application Characteristics under Multi-tube Coupled Heat Transfer

被引：0
|
作者：
Zhang Z. [1 ]
Tan S. [1 ]
Li X. [2 ]
Liu S. [1 ]
Feng Y. [1 ]
Huang Y. [1 ]
Tian R. [1 ]
机构：
[1] College of Nuclear Science and Technology, Harbin Engineering University, Harbin
[2] College of Aerospace and Civil Engineering, Harbin Engineering University, Harbin
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2024年 / 45卷 / 02期
关键词：
Coupled heat transfer; Eulerian two-fluid multiphase model; Flow boiling; Numerical simulation; OSTG;
D O I：
10.13832/j.jnpe.2024.02.0130
中图分类号：
学科分类号：
摘要：
Aiming at the problems of high difficulty in simulation, low computational efficiency, and large uncertainties when applying the method of computational fluid dynamics (CFD) to the analysis of coupled heat transfer on primary and secondary sides and full-regime flow boiling heat transfer in once-through steam generator (OTSG), based on the Eulerian two-fluid multiphase model and the critical heat flux density (CHF) wall boiling model, a numerical analysis model of the full-regime flow boiling heat transfer in the tube is established, and the effectiveness of the model is verified. Based on the verified model, the application characteristics of the numerical model under multi-tube coupling heat transfer are studied, the reliability of the numerical simulation method under multi-tube coupling is clarified, and the sensitivity of the calculation results of temperature and phase distribution to the interphase force model is numerically analyzed. The results show that based on Euler's two-fluid multiphase flow model and CHF wall boiling model, the full-regime flow boiling heat transfer process of water in the tube from supercooling to overheating can be predicted accurately. The location of dry-out point and the peak temperature of the wall are in good agreement with the experimental values, with a maximum error of less than 10%. The numerical method based on Euler two-fluid multiphase flow model and CHF wall boiling model has good applicability to multi-tube coupling conditions, and the calculated secondary side temperature is in good agreement with the experimental results. The interphase drag force has obvious influence on the calculation results of wall temperature and cavitation share, but the non-drag force has little influence on wall temperature. Therefore, for large-scale engineering application calculation, the influence of some interphase non-drag forces may not be considered in the analysis. The results of this paper can provide useful reference for the model selection of OSTG's three-dimensional refined numerical analysis. © 2024 Atomic Energy Press. All rights reserved.
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页码：130 / 138
页数：8
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