Numerical Simulation of PRHR System Based on CFD

DOI: 10.4236/jamp.2013.16015   PDF   HTML     3,146 Downloads   4,720 Views   Citations

Abstract

In this paper numerical simulation of PRHR HX and IRWST is demonstrated using FLUENT, and different numbers of C-type heat transfer tubes and coolant inlet temperature’s effects for the residual heat removal capacity of PRHR HX, IRWST thermal stratification and natural circulation have been researched. It’s found that at a constant flow area when heat transfer tubes’ number increased outlet temperature of PRHR HX is lower, the whole water temperature of IRWST is higher, thermal stratification and natural circulation are more oblivious. At a constant mass flow when inlet temperature of PRHR HX increased, inlet flow velocity increases and outlet temperature is higher. But on the other hand the cooling rate increases at the same time, the average temperature of IRWST is higher, the range of thermal stratification expands and the velocity of natural circulation increases.

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Jia, B. , Jing, J. , Qiao, X. and Zhang, C. (2013) Numerical Simulation of PRHR System Based on CFD. Journal of Applied Mathematics and Physics, 1, 74-81. doi: 10.4236/jamp.2013.16015.

Conflicts of Interest

The authors declare no conflicts of interest.

References

[1] C.G. Lin and Z.S. Yu, “Passive Safety Advanced Power Plant AP1000,” Atomic Energy Press, Beijing, 2008.
[2] K. Ikeda, Y. Makino and M. Hoshi, “Single-Phase CFD Applicability for Estimating Fluid Hot-Spot Locations in a 5*5 Fuel Rod Bundle,” Nuclear Engineering and Design, Vol. 236, No. 11, 2006, pp. 1149-1154. http://dx.doi.org/10.1016/j.nucengdes.2005.11.006
[3] M. Kim, S. O. Yu and H. J. Kim, “Analyses on Fluid Flow and Heat Transfer inside Calandria Vessel of CANDU-6 Using CFD,” Nuclear Engineering and Design, Vol. 236, No. 11, 2006, pp. 1155-1164. http://dx.doi.org/10.1016/j.nucengdes.2005.10.018
[4] L.S. Li, K. Wang and X.M. Song, “International Research Progress of CFD Application in Analysis of Nuclear Power System,” Nuclear Power Engineering, Vol. 30, No. 5, 2009, pp. 28-33.
[5] Y.J. Gao, “Analysis of Fabrication Process for AP1000 Passive Residual Heat Removal Heat Exchanger,” Nuclear Power Engineering, Vol. 32, No. 2, 2011, pp. 107- 111.
[6] R.J. Xue, C.C. Deng and M.J. Peng, “Numerical Simulation of Passive Residual Heat Removal Heat Exchanger,” Atomic Energy Science and Technology, Vol. 44, No. 4, 2010, pp. 429-435.
[7] T.Z. Ming, “Passive Residual Heat Removal Heat Exchanger Numiral Simulation and Design Research,” Huazhong University of Science and Technology, Wuhan, 2003.
[8] Y.B. Su, J. Lu and B.F. Bai, “Numerical Simulation of Natural Convection and Heat Transfer of Water in Cavities,” Journal of Chemical Industry and Engineering (China), Vol. 58, No. 11,2007, pp. 2715-2720.
[9] S.M. Yang and W.Q. Tao, “Heat Transfer,” 4th Edition, Higher Education Press, Beijing, 2006.

  
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