Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Research on flow characteristics in supercritical water natural circulation: Influence of heating power distribution

  • Ma, Dongliang (School of Nuclear Science and Engineering, North China Electric Power University) ;
  • Zhou, Tao (School of Nuclear Science and Engineering, North China Electric Power University) ;
  • Feng, Xiang (School of Nuclear Science and Engineering, North China Electric Power University) ;
  • Huang, Yanping (Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China)
  • 투고 : 2018.03.20
  • 심사 : 2018.07.11
  • 발행 : 2018.10.25
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초록

There are many parameters that affect the natural circulation flow, such as height difference, heating power size, pipe diameter, system pressure and inlet temperature and so on. In general analysis the heating power is often regarded as a uniform distribution. The ANSYS-CFX numerical analysis software was used to analyze the flow heat transfer of supercritical water under different heating power distribution conditions. The distribution types of uniform, power increasing, power decreasing and sine function are investigated. Through the analysis, it can be concluded that different power distribution has a great influence on the flow of natural circulation if the total power of heating is constant. It was found that the peak flow of supercritical water natural circulation is maximal when the distribution of heating power is monotonically decreasing, minimal when it is monotonically increasing, and moderate at uniform or the sine type of heating. The simulation results further reveal the supercritical water under different heat transfer conditions on its flow characteristics. It can provide certain theory reference and system design for passive residual heat removal system about supercritical water.

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참고문헌

  1. V. Chatoorgoon, A. Voodi, D. Fraser, The stability boundary for supercritical flow in natural convection loops Part I: $H_2O$ studies, Nucl. Eng. Des. 235 (2005) 2570-2580. https://doi.org/10.1016/j.nucengdes.2005.06.003
  2. Zhang Youjie, Jiang Shengyao, Wu Shaorong, Experiment study on effect of distribution of heating power density on stability of two phase flow [J], Nucl. Power Eng. (3) (1998), 239-232.
  3. Cheng Heping, Zhang Zongyao, Yu Junchong, Reactor axial power distribution control and power capability analysis, China Nucl. Sci. Technol. Rep. (00) (1995) 810-823.
  4. L.I. Huixiong, S.U.N. Shuweng, G.U.O. Bin, et al., Experimental investigation on the circumferential ununiformity in heat transfer of water in inclined smooth upward tubes at supercritical pressures, J. Eng. Thermophys. 29 (2) (2008) 241-245. https://doi.org/10.1007/s10765-007-0337-1
  5. L.E.I. Xianliang, L.I. Huixiong, Y.U. Shuiqing, et al., Numerical simulation on heterogeneous heat transfer in water at supercritical pressures in inclined upward tubes, Chin. J. Comput. Phys. 27 (2) (2010) 217-228. https://doi.org/10.3969/j.issn.1001-246X.2010.02.009
  6. Lu Xiaodong, Chen Bingde, Wang Yanlin, et al., Effect of axial power distributions on supercritial water flow instability, Nucl. Power Eng. (3) (2017) 1-6.
  7. J.I.A. Jian, L.I.U. Zhihong, Research of core power distribution reconstruction method based on cross-section deviation, Atomic Energy Sci. Technol. 51 (1) (2017) 89-94.
  8. C.A.O. Pan, Y.U. Hong, X.U. Li, et al., Research on pin power distribution in fuel subassembly of fast reactor, Atomic Energy Sci. Technol. 47 (b06) (2013) 287-290.
  9. Cheng Sheng, Tao Zhou, Jingjing Li, et al., Nonlinear Analysis of Natural Circulation Critical Heat Flux in Narrow Channel, 46, 2012, pp. 1330-1335 (11).
  10. M.K. Rowinski, J. Zhao, T.J. White, et al., Numerical investigation of supercritical water flow in a vertical pipe under axially non-uniform heat flux, Prog. Nucl. Energy 97 (2017) 11-25. https://doi.org/10.1016/j.pnucene.2016.12.009
  11. S. Paul, S. Singh, On nonlinear dynamics of density wave oscillations in a channel with non-uniform axial heating, Int. J. Therm. Sci. 116 (2017) 172-198. https://doi.org/10.1016/j.ijthermalsci.2017.02.008
  12. S. Paul, S. Singh, Analysis of local bifurcations in a channel subjected to non-uniform axial heating, Int. J. Heat Mass Tran. 108 (2017) 2143-2157. https://doi.org/10.1016/j.ijheatmasstransfer.2017.01.060
  13. M. Rowinski, Y.C. Soh, T.J. White, et al., Numerical investigation of supercritical water flow in a $2{\times}2$ rod bundle under non-uniform heat flux, in: International Conference on Nuclear Engineering, 2016. V005T15A012.
  14. Omar S. Al-Yahia, Taewoo Kim, Daeseong Jo, Experimental study of uniform and non-uniform transverse heat flux distribution effect on the onset of nucleate boiling, in: International Conference on Nuclear Engineering, 2017.
  15. M.A. Habib, M.A. Nemitallah, M. El-Nakla, Current status of CHF predictions using CFD modeling technique and review of other techniques especially for non-uniform axial and circumferential heating profiles, Ann. Nucl. Energy 70 (70) (2014) 188-207.
  16. D. Lucas, R. Rzehak, E. Krepper, et al., A strategy for the qualification of multifluid approacheds for nuclear reactor safety, Nucl. Eng. Des. 299 (2016) 2-11. https://doi.org/10.1016/j.nucengdes.2015.07.007
  17. Y. Liao, D. Lucas, E. Krepper, et al., Flashing evaporation under different pressure levels, Nucl. Eng. Des. 265 (2013) 801-813. https://doi.org/10.1016/j.nucengdes.2013.09.027
  18. J. Tang, M. Huang, Y. Zhao, et al., A new procedure for solving steady-state and transient-state nonlinear radial conduction problems of nuclear fuel rods, Ann. Nucl. Energy 110 (2017) 492-500. https://doi.org/10.1016/j.anucene.2017.05.061
  19. M. Huang, J. Tang, Y. Zhao, et al., A new efficient and accurate procedure for solving heat conduction problems, Int. J. Heat Mass Tran. 111 (2017) 508-519. https://doi.org/10.1016/j.ijheatmasstransfer.2017.03.109
  20. ANSYS, Inc, ANSYS CFX Solver Theory Guide, 2015. Canonsburg, PA.