Investigation on the Critical Flow Through a Rectangular Narrow Slit

被引：2
|
作者：
Huang B. [1 ]
Zhang B. [1 ]
Sun Y. [1 ]
Gong S. [1 ]
机构：
[1] School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai
来源：
Hsi-An Chiao Tung Ta Hsueh/Journal of Xi'an Jiaotong University | 2020年 / 54卷 / 05期
关键词：
Critical flow; Henry-Fauske model; LBB analysis; Thermodynamic non-equilibrium;
D O I：
10.7652/xjtuxb202005004
中图分类号：
学科分类号：
摘要：
Critical flow experiments through a rectangular narrow slit were conducted based on the leakage rate of the coolant through crack in the LBB analysis of nuclear power plant pipe system. The test section with a structure size of 80 mm×10 mm×0.6 mm was used to investigate the influences of upstream pressure and temperature on the critical flowrate, within the upstream pressure range of 4-12 MPa and subcooling range of 10-125℃. The Henry-Fauske critical flow calculation model was modified by introducing Richter's flashing superheat prediction formula because of the observed thermodynamic non-equilibrium in experiments. Results show that the critical flowrate increases with the upstream pressure and subcooling. In addition, the thermodynamic non-equilibrium is more obvious for the cases with lower upstream subcooling. The location of the flashing inception moves to the upstream with the decrease of upstream subcooling and has a great impact on critical flowrate, which can be predicted by the modified Henry-Fauske model. The predicted results of the critical flowrate by the improved model show a good agreement with the experimental data with an error of ±10%. © 2020, Editorial Office of Journal of Xi'an Jiaotong University. All right reserved.
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页码：26 / 31
页数：5
相关论文
共 17 条
  • [1] Fang Y., Wang Q., Su Y., Et al., Study on differences of LBB and BP concepts applied to high energy pipe of nuclear power plant, Nuclear Safety, 16, 4, pp. 61-65, (2017)
  • [2] Beniussa K., Hedner G., Cakmak E., Et al., European safety practices on the application of leak before break (LBB) concept: EUR18549, (2000)
  • [3] Scott P.M., Olson R.J., Wilkowski G.M., Development of technical basis for leak-before-break evaluation procedures: NUREG/CR-6765, (2002)
  • [4] Chen T., Xu J., Luo Y., Experimental study on two-phase critical flow, Journal of Engineering Thermophysics, 23, 5, pp. 623-626, (2002)
  • [5] Chen Y., Yang C., Zhang S., Et al., Evaluation of existing physical models on critical flow based on experiment with a nozzle, Atomic Energy Science and Technology, 43, 6, pp. 485-490, (2009)
  • [6] Yang Z., Bi Q., Zhu G., Et al., Leak rates of high pressure steam-water across simulation crack, Experimental Thermal and Fluid Science, 59, pp. 118-126, (2014)
  • [7] Zhang J., Chen R.H., Wang M.J., Et al., Prediction of LBB leakage for various conditions by genetic neural network and genetic algorithms, Nuclear Engineering and Design, 325, pp. 33-43, (2017)
  • [8] Yin H., Liang B., Xu N., Development of leak rate calculation model and code in piping, Nuclear Techniques, 36, 4, pp. 90-93, (2013)
  • [9] Park J.H., Cho Y.K., Kim S.H., Et al., Estimation of leak rate through circumferential cracks in pipes in nuclear power plants, Nuclear Engineering and Technology, 47, 3, pp. 332-339, (2015)
  • [10] John H., Reimann J., Westphal F., Et al., Critical two-phase flow through rough slits, International Journal of Multiphase Flow, 14, 2, pp. 155-174, (1988)
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