Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR

  • Wang, Yingjie (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Wang, Mingjun (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Ju, Haoran (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Zhao, Minfu (China Institute of Atomic Energy) ;
  • Zhang, Dalin (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Tian, Wenxi (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Liu, Tiancai (China Institute of Atomic Energy) ;
  • Qiu, Suizheng (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University) ;
  • Su, G.H. (School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University)
  • Received : 2019.07.28
  • Accepted : 2019.12.12
  • Published : 2020.07.25
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Abstract

High fidelity nuclear reactor fuel assembly simulation using CFD method is an effective way for the structure design and optimization. The validated models and user practice guidelines play critical roles in achieving reliable results in CFD simulations. In this paper, the international benchmark MATiS-H is studied carefully and the best user practice guideline is achieved for the rod bundles simulation. Then a 5 × 5 rod bundles model in the advanced pressurized water reactor (PWR) is established and the detailed three-dimensional thermal-hydraulic characteristics are investigated. The influence of spacer grids and mixing vanes on the flow and hear transfer in rod bundles is revealed. As the coolant flows through the spacer grids and mixing vanes in the rod bundles, the drastic lateral flow would be induced and the pressure drop increases significantly. In addition, the heat transfer is enhanced remarkably due to the strong mixing effects. The calculation results could provide meaningful guidelines for the design of advanced PWR fuel assembly.

Keywords

References

  1. M. Hassan, K. Rehme, Heat transfer near spacer grids in gas-cooled rod bundles, Nucl. Technol. 52 (3) (1981) 401-414. https://doi.org/10.13182/NT81-A32714
  2. Y.F. Shen, Z.D. Cao, Q.G. Lu, An investigation of crossflow mixing effect caused by grid spacer with mixing blades in a rod bundle, Nucl. Eng. Des. 125 (2) (1991) 111-119. https://doi.org/10.1016/0029-5493(91)90071-O
  3. Sun Kyu Yang, Moon Ki Chung, Spacer grid effects on turbulent flow in rod bundles, Journal of the Korean Nuclear Society 28 (1996). Number 1.
  4. Diana Caraghiaur, Henryk Anglart, et al., Experimental investigation of turbulent flow through spacer grids in fuel rod bundles, Nucl. Eng. Des. 239 (2009) 2013-2021. https://doi.org/10.1016/j.nucengdes.2009.05.029
  5. H.L. McClusky, M.V. Holloway, T.A. Conover, et al., Mapping of the lateral flow field in typical subchannels of a support grid with vanes, Journal of Fluids Egineering 125 (6) (2003) 987-996. https://doi.org/10.1115/1.1625688
  6. E.E. Dominguez-Ontiveros, Y.A. Hassan, Non-intrusive experimental investigation of flow behavior inside a $5{\times}5$ rod bundle with spacer grids using PIV and MIR, Nucl. Eng. Des. 239 (5) (2009) 888-898. https://doi.org/10.1016/j.nucengdes.2009.01.009
  7. S.S. Paul, S.J. Ormiston, et al., Experimental and numerical investigation of turbulent cross-flow in a staggered tube bundle, Int. J. Heat Fluid Flow 29 (2008) 387-414. https://doi.org/10.1016/j.ijheatfluidflow.2007.10.001
  8. Haoran Ju, Mingjun Wang, Chong Chen, Xiaohan Zhao, Minfu Zhao, Wenxi Tian, G.H. Su, Suizheng Qiu, Numerical study on the turbulent mixing in channel with Large Eddy Simulation (LES) using spectral element method, Nucl. Eng. Des. 348 (2019) 169-176. https://doi.org/10.1016/j.nucengdes.2019.04.017
  9. Xiaohan Zhao, Mingjun Wang, Chong Chen, Xi Wang, Haoran Ju, Wenxi Tian, Suizheng Qiu, G.H. Su, Three-dimensional study on the hydraulic characteristics under the steam generator (SG) tube plugging operations for AP1000, Prog. Nucl. Energy 112 (2019) 63-74. https://doi.org/10.1016/j.pnucene.2018.10.016
  10. Tangtao Feng, Mingjun Wang, Ping Song, Luguo Liu, Wenxi Tian, G.H. Su, Suizheng Qiu, Numerical research on thermal mixing characteristics in a 45-degree T-junction for two-phase stratified flow during the emergency core cooling safety injection, Prog. Nucl. Energy 114 (2019) 91-104. https://doi.org/10.1016/j.pnucene.2019.03.009
  11. Mingjun Wang, Di Fang, Yan Xiang, Yi Fei, Yun Wang, Wuyue Ren, Wenxi Tian, G.H. Su, Suizheng Qiu, Study on the coolant mixing phenomenon in a 45 degrees T junction based on the thermal-mechanical coupling method, Appl. Therm. Eng. 144 (2018) 600-613. https://doi.org/10.1016/j.applthermaleng.2018.08.073
  12. Moyses A. Navarro, Andre A.C. Santos, Evaluation of a numeric procedure for flow simulation of a $5{\times}5$ PWR rod bundle with a mixing vane spacer, International Nuclear Atlantic Conference - INAC (2009).
  13. K. Ikeda, Y. Makino, M. Hoshi, Single-phase CFD applicability for estimating fluid hot-spot locations in a $5{\times}5$ fuel rod bundle, J. Nucl. Eng. Des. 236 (11) (2006) 1149-1154. https://doi.org/10.1016/j.nucengdes.2005.11.006
  14. A. Gandhir, Y. Hassan, RANS modeling for flow in nuclear fuel bundle in pressurized water reactors(PWR), Nucl. Eng. Des. 241 (2011) 4404-4408. https://doi.org/10.1016/j.nucengdes.2011.08.084
  15. Y.S. Teng, Y.M. Ferng, C.H. Lin, Investigating flow and heat transfer characteristics in a fuel bundle with split-vane pair grids by CFD methodology, Ann. Nucl. Energy 64 (2014) 93-99. https://doi.org/10.1016/j.anucene.2013.09.037
  16. Podila Krishna, Yanfei Rao, CFD modelling of turbulent flows through $5{\times}5$ fuel rod bundles with spacer-grids, Ann. Nucl. Energy 97 (2016) 86-95. https://doi.org/10.1016/j.anucene.2016.07.003
  17. N. Cinosi, S.P. Walker, et al., CFD simulation of turbulent flow in a rod bundle with spacer grids(MATIS-H) using STAR-CCM+, Nucl. Eng. Des. 279 (2014) 37-49. https://doi.org/10.1016/j.nucengdes.2014.06.019
  18. C.C. Liu a, Y.M. Ferng, CFD evaluation of turbulence models for flow simulation of the fuel rod bundle with a spacer assembly, Appl. Therm. Eng. 40 (2012) 389-396. https://doi.org/10.1016/j.applthermaleng.2012.02.027
  19. Blaz Mikuz, Iztok Tiselj, URANS prediction of flow fluctuations in rod bundle with split-type spacer grid, Int. J. Heat Fluid Flow 64 (2017) 10-22. https://doi.org/10.1016/j.ijheatfluidflow.2017.01.008
  20. Blaz Mikuz, Iztok Tiselj, Wall-resolved Large Eddy Simulation in grid-free $5\;{\times}\;5$ rod bundle of MATiS-H experiment, Nucl. Eng. Des. 298 (2016) 64-77. https://doi.org/10.1016/j.nucengdes.2015.12.021
  21. J.R. Lee, J. Kim, C.-H. Song, Synthesis of the turbulent mixing in a rod bundle with vaned spacergrids based on the OECD-KAERI CFD benchmark exercise, Nucl. Eng. Des. 279 (2014) 3-18. https://doi.org/10.1016/j.nucengdes.2014.03.008
  22. ANSYS Inc, FLUENT -theory guide, Release 15.0 (2014a).
  23. B.L. Smith, C.H. Song, S.K. Chang, J.R. Lee, J.W. Kim, Report of the OECD/NEA KEARI Rod Bundle CFD Benchmark Exercise[M], NEA/CSNI/R, 2013, p. 5.
  24. M.C. Misvel, M.E. Conner, R.P. Knott, DESIGN and DEVELOPMENT of the FUEL ASSEMBLY for the WESTINGHOUSE AP1000 REACTOR[R]. Chengdu, China, 2011.
  25. M. Malicki, L. Pienkowski,K. Skolik, A.K. Trivedi, Development of MELCOR thermal hydraulic model of AP1000 and its verification for a DECL break, Ann. Nucl. Energy 128 (2019) 44-52. https://doi.org/10.1016/j.anucene.2018.12.041
  26. B.N. Friedman, The AP1000 plant and the China project commissioning success, J. Nucl. Eng. Radiat. Sci. (2018).

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