DOI QR코드

DOI QR Code

Heat transfer analysis in sub-channels of rod bundle geometry with supercritical water

  • Shitsi, Edward (Department of Nuclear Engineering, Graduate School of Nuclear and Allied Sciences, University of Ghana) ;
  • Debrah, Seth Kofi (Department of Nuclear Engineering, Graduate School of Nuclear and Allied Sciences, University of Ghana) ;
  • Chabi, Silas (Department of Nuclear Engineering, Graduate School of Nuclear and Allied Sciences, University of Ghana) ;
  • Arthur, Emmanuel Maurice (Department of Nuclear Engineering, Graduate School of Nuclear and Allied Sciences, University of Ghana) ;
  • Baidoo, Isaac Kwasi (National Nuclear Research Institute, Ghana Atomic Energy Commission GAEC)
  • 투고 : 2021.03.05
  • 심사 : 2021.09.24
  • 발행 : 2022.03.25

초록

Parametric studies of heat transfer and fluid flow are very important research of interest because the design and operation of fluid flow and heat transfer systems are guided by these parametric studies. The safety of the system operation and system optimization can be determined by decreasing or increasing particular fluid flow and heat transfer parameter while keeping other parameters constant. The parameters that can be varied in order to determine safe and optimized system include system pressure, mass flow rate, heat flux and coolant inlet temperature among other parameters. The fluid flow and heat transfer systems can also be enhanced by the presence of or without the presence of particular effects including gravity effect among others. The advanced Generation IV reactors to be deployed for large electricity production, have proven to be more thermally efficient (approximately 45% thermal efficiency) than the current light water reactors with a thermal efficiency of approximately 33 ℃. SCWR is one of the Generation IV reactors intended for electricity generation. High Performance Light Water Reactor (HPLWR) is a SCWR type which is under consideration in this study. One-eighth of a proposed fuel assembly design for HPLWR consisting of 7 fuel/rod bundles with 9 coolant sub-channels was the geometry considered in this study to examine the effects of system pressure and mass flow rate on wall and fluid temperatures. Gravity effect on wall and fluid temperatures were also examined on this one-eighth fuel assembly geometry. Computational Fluid Dynamics (CFD) code, STAR-CCM+, was used to obtain the results of the numerical simulations. Based on the parametric analysis carried out, sub-channel 4 performed better in terms of heat transfer because temperatures predicted in sub-channel 9 (corner subchannel) were higher than the ones obtained in sub-channel 4 (central sub-channel). The influence of system mass flow rate, pressure and gravity seem similar in both sub-channels 4 and 9 with temperature distributions higher in sub-channel 9 than in sub-channel 4. In most of the cases considered, temperature distributions (for both fluid and wall) obtained at 25 MPa are higher than those obtained at 23 MPa, temperature distributions obtained at 601.2 kg/h are higher than those obtained at 561.2 kg/h, and temperature distributions obtained without gravity effect are higher than those obtained with gravity effect. The results show that effects of system pressure, mass flowrate and gravity on fluid flow and heat transfer are significant and therefore parametric studies need to be performed to determine safe and optimum operating conditions of fluid flow and heat transfer systems.

키워드

과제정보

The authors are very grateful to Cd-Adapco for making it possible for the STAR-CCM + CFD code to be used at a reduced license fee. Prof. Walter Ambrosini of University of Pisa is also acknowledged for his technical support in developing cubic spline program which makes it possible for water and other coolants properties to be obtained.

참고문헌

  1. M.M. Rahman, J. Dongxu, N. Jahan, M. Salvatores, J. Zhao, Design concepts of supercritical water-cooled reactor (SCWR) and nuclear marine vessel: a review, Prog. Nucl. Energy 124 (2020) 103320. https://doi.org/10.1016/j.pnucene.2020.103320
  2. L. Castro, J.-L. Francois, C. Garcia, Coupled Monte Carlo-CFD analysis of heat transfer phenomena in a supercritical water reactor fuel assembly, Ann. Nucl. Energy 141 (2020) 107312. https://doi.org/10.1016/j.anucene.2020.107312
  3. X. Hao, P. Xu, H. Suo, L. Guo, Numerical investigation of flow and heat transfer of supercritical water in the water-cooled wall tube, Int. J. Heat Mass Tran. (2019), https://doi.org/10.1016/j.ijheatmasstransfer.2019.119084.
  4. Z. Zhang, C. Zhao, X. Yang, P. Jiang, J. Tu, S. Jiang, Numerical study of the heat transfer and flow stability of water at supercritical pressures in a vertical tube, Nucl. Eng. Des. 325 (2017) 1-11. https://doi.org/10.1016/j.nucengdes.2017.09.013
  5. Z. Shen, D. Yang, S. Wang, W. Wang, Y. Li, Experimental and numerical analysis of heat transfer to water at supercritical pressures, Int. J. Heat Mass Tran. 108 (2017) 1676-1688. https://doi.org/10.1016/j.ijheatmasstransfer.2016.12.081
  6. M. Jaromin, H. Anglart, A numerical study of heat transfer to supercritical water flowing upward in vertical tubes under normal and deteriorated conditions, Nucl. Eng. Des. 264 (2013) 61-70. https://doi.org/10.1016/j.nucengdes.2012.10.028
  7. G. Zhang, H. Zhang, H. Gu, Y. Yang, X. Cheng, Experimental and numerical investigation of turbulent convective heat transfer deterioration of supercritical water in vertical tube, Nucl. Eng. Des. 248 (2012) 226-237. https://doi.org/10.1016/j.nucengdes.2012.03.026
  8. W. Gang, J. Pan, Q. Bi, Z. Yang, H. Wang, Heat transfer characteristics of supercritical pressure water in vertical upward annuli, Nucl. Eng. Des. 273 (2014) 449-458. https://doi.org/10.1016/j.nucengdes.2014.03.038
  9. H. Wang, Q. Bi, L. Wang, H. Lv, L.K.H. Leung, Experimental investigation of heat transfer from a 2×2 rod bundle to supercritical pressure water, Nucl. Eng. Des. 275 (2014) 205-218. https://doi.org/10.1016/j.nucengdes.2014.04.036
  10. M. Qu, D. Yang, Z. Liang, L. Wan, D. Liu, Experimental and numerical investigation on heat transfer of ultra-supercritical water in vertical upward tube under uniform and non-uniform heating, Int. J. Heat Mass Tran. 127 (2018) 769-783. https://doi.org/10.1016/j.ijheatmasstransfer.2018.08.079
  11. Z. Gao, J. Bai, Numerical analysis on non-uniform heat transfer of supercritical pressure water in horizontal circular tube, Appl. Therm. Eng. 120 (2017) 10-18. https://doi.org/10.1016/j.applthermaleng.2017.03.109
  12. F. Li, B. Bai, Flow and heat transfer of supercritical water in the vertical helically-coiled tube under half-side heating condition, Appl. Therm. Eng. 133 (2018) 512-519. https://doi.org/10.1016/j.applthermaleng.2018.01.047
  13. H.B. Li, M. Zhao, Z.X. Hu, H.Y. Gu, D.H. Lu, Experimental study on transient heat transfer across critical pressure in 2×2 rod bundle with wire wraps, Int. J. Heat Mass Tran. 110 (2017) 68-79. https://doi.org/10.1016/j.ijheatmasstransfer.2017.03.013
  14. H.Y. Gu, H.B. Li, Z.X. Hu, D. Liu, Heat transfer to supercritical water in a 2×2 rod bundle, Ann. Nucl. Energy 83 (2015) 114-124. https://doi.org/10.1016/j.anucene.2015.04.020
  15. J. Chen, Z. Xiong, Y. Xiao, H. Gu, Experimental study on the grid-enhanced heat transfer at supercritical pressures in rod bundle, Appl. Therm. Eng. 156 (2019) 299-309. https://doi.org/10.1016/j.applthermaleng.2019.04.073
  16. H. Lv, Q. Bi, X. Dong, Z. Zhang, G. Zhu, Investigation on heat transfer of in-tube supercritical water cooling accompanying out-tube pool boiling, Int. J. Heat Mass Tran. 136 (2019) 938-949. https://doi.org/10.1016/j.ijheatmasstransfer.2019.03.069
  17. S. Chen, H. Gu, M. Liu, Y. Xiao, D. Cui, Experimental investigation on heat transfer to supercritical water in a three rod bundle with spacer grids, Appl. Therm. Eng. 164 (2020) 114466. https://doi.org/10.1016/j.applthermaleng.2019.114466
  18. S.E.-D. El-Morshedy, S.M.A. Ibrahim, A. Alyan, A. Abdelmaksoud, Heat transfer deterioration mechanism for water at supercritical pressure, International Journal of Thermofluids 7-8 (2020) 100020.
  19. S.K. Debrah, E. Shitsi, S. Chabi, N. Sahebi, Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor, Heliyon 5 (2019), e02927. https://doi.org/10.1016/j.heliyon.2019.e02927
  20. K. Podila, Y.K. Rao, CFD analysis of flow and heat transfer in Canadian supercritical water reactor bundle, Ann. Nucl. Energy 75 (2014) 1-10. https://doi.org/10.1016/j.anucene.2014.07.039
  21. CD-ADAPCO, User Guide STAR-CCM+, 2015. Version 10.06.009", New York.
  22. X. Xi, Z. Xiao, X. Yan, T. Xiong, Y. Huang, Numerical simulation of the flow instability between two heated parallel channels with supercritical water, Ann. Nucl. Energy 64 (2014b) 57-66. https://doi.org/10.1016/j.anucene.2013.09.017
  23. E. Shitsi, S.K. Debrah, V.Y. Agbodemegbe, E. Ampomah-Amoako, Numerical investigation of heat transfer in parallel channels with water at supercritical pressure, Heliyon 3 (11) (2017), e00453. https://doi.org/10.1016/j.heliyon.2017.e00453
  24. C.L. Waata, Coupled Neutronics/Thermal-Hyhdraulics Analysis of a High Performance Light Water Reactor Fuel Assembly, PhD Thesis, 2006, p. 104.
  25. Zhirui Zhao, Yitung Chen, Baozhi Sun, Jianxin Shi, Xiang Yu, Wanze Wu, Nonuniform thermal-hydraulic behavior in a 61-rod bundle of supercritical water-cooled reactor, Appl. Therm. Eng. 171 (2020), https://doi.org/10.1016/j.applthermaleng.2019.114688, 114688.