Influence of Physical Model and Boundary Condition on Two-phase Flow Instability Boundary in Once-through Evaporation Tube

被引:0
|
作者
Su Y. [1 ]
Li X. [1 ]
Yan H. [1 ]
Wu X. [1 ]
Liang Q. [1 ]
机构
[1] Institute of Nuclear and New Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing
关键词
Constant flow rate; Constant pressure drop; Instability boundary; Power distribution; Steam generator; Two-phase flow instability;
D O I
10.7538/yzk.2018.youxian.0828
中图分类号
学科分类号
摘要
The effects of different boundary conditions and physical models on two-phase flow instability boundary were studied in this paper. In order to verify the code and model, the RELAP5 code was used to simulate two-phase flow instability experiments in once-through evaporation tube. Then the influences of constant flow rate and constant pressure drop boundary conditions, the number of parallel tubes, the axial power distribution patterns and the heat capacity of the heat transfer tubes on the instability boundary were analyzed. The results show that the instability boundary differences among single tube, two tubes and multiple tube models are less than 5% under constant pressure drop boundary conditions. Under constant flow rate boundary conditions, the instability boundary of multiple tube models differs from that of two tubes model by less than 5%, while the instability boundary of single tube model differs from that of two tubes models by more than 100%. When the numbers of parallel tubes in the models are the same, the stability of the model with the constant flow rate boundary conditions is better than that with the constant pressure drop boundary conditions. The stability of the system with increasing power distribution along the flow direction (axial direction) is better than that with uniform power distribution, and the stability of the system with uniform power distribution along the flow direction is better than that with decreasing power distribution. When the wall thickness varies from 0 to 20 mm, the wall heat capacity has little effect on the instability boundary. © 2019, Editorial Dept. of JA. All right reserved.
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页码:624 / 631
页数:7
相关论文
共 11 条
  • [1] Boure J.A., Bergles A.E., Tong L.S., Review of two-phase flow instability, Nuclear Engineering and Design, 25, 2, pp. 165-192, (1973)
  • [2] Lahey R.T., Podowski M.Z., On the analysis of various instabilities in two-phase flows, Multiphase Science & Technology, 4, 1-4, pp. 183-370, (1989)
  • [3] Ma Y., Li X., Wu X., Thermal-hydraulic characteristics and flow instability analysis of an HTGR helical tube steam generator, Annals of Nuclear Energy, 73, 1, pp. 484-495, (2014)
  • [4] Hirayama M., Umekawa H., Ozawa M., Parallel-channel instability in natural circulation system, Multiphase Science & Technology, 18, 4, pp. 305-333, (2006)
  • [5] Ma Y., Li X., Wu X., Transient numerical simulation and two-phase flow instability prediction of convective boiling in vertical up-flow tube, Atomic Energy Science and Technology, 47, 12, pp. 2249-2253, (2013)
  • [6] Ambrosini W., Ferreri J.C., Analysis of basic phenomena in boiling channel instabilities with different flow models and numerical schemes, International Conference on Nuclear Engineering, pp. 889-900, (2006)
  • [7] Fu W., Li X., Wu X., Et al., Investigation on two-phase flow density wave instability in parallel once-through evaporatiom tubes, Journal of Engineering Thermophysics, 35, 3, pp. 576-580, (2014)
  • [8] Marco C., Antonio C., Davide P., Et al., RELAP5/MOD3.3 study on density wave instabilities in single channel and two parallel channels, Progress in Nuclear Energy, 56, 4, pp. 15-23, (2012)
  • [9] Xia G., Peng M., Guo Y., Research of two-phase flow instability in parallel narrow multi-channel system, Annals of Nuclear Energy, 48, 48, pp. 1-16, (2012)
  • [10] Takitani K., Takemura T., Density wave instability in once-through boiling flow system, Ⅰ, Journal of Nuclear Science & Technology, 15, 5, pp. 355-364, (1978)