Page 239 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
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210                   Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors


                              2150
                            Max. fuel temperature (°C)  2050
                              2100


                              2000

                              1950
                              1900
                              1850
                                  0   20   40   60   80  100
                                        Fuel pin number
         Fig. 5.18 Maximum fuel temperatures.


         References

         Carluec, B., Abderrahim, H. Aid, M€ uller, A.C., 2002. The European Program, 3rd Int. Work-
             shop on Utilization and Reliability of High-Power Proton Accelerators, Santa Fe, NM,
             May 12–16.
         Cheng, X., 2006. Subchannel analysis of fuel assemblies of European experimental ADS, Nucl.
             Technol., vol. 154, no. 1, pp. 52–68, 2006.
         Cheng, X., Tak, N.I., 2006. CFD analysis of thermal–hydraulic behavior of heavy liquid metals
             in sub-channels, Nucl. Eng. Des., vol. 236, no. 18, pp. 1874–1885, 2006.
         Cheng, S.K., Todreas, N., 1982. Hydrodynamic models and correlations for bare and wire-
             wrapped hexagonal rod bundles – bundle friction factors, sub-channel friction factors
             and mixing parameters. Nucl. Eng. Des. 92 (1982), 227–251.
         Cheng, X., Batta, A., Tak, N.I 2006. Investigation on turbulent heat transfer to lead–bismuth
             eutectic flows in circular tubes for nuclear applications, Nucl. Eng. Des., vol. 236, no.
             4, pp. 385–393, 2006.
         Colebrook, C.F., 1939. Turbulent flow in pipes, with particular reference to the transition region
             between the smooth and rough pipe laws. J. ICE 11 (4), 133–156.
         Huber, K., 2017. A Multiscale Method for Mixed Convection Systems: Coupled Calculations
             With ATHLET and OpenFOAM of the PHENIX NCT. PhD thesis, Karlsruhe Institute of
             Technology (KIT).
         Ibragimov, M., Subbotin, V.I., Ushakov, P.A., 1960. Investigation of heat transfer in the turbu-
             lent flow of liquid metals in tubes. Atomnaya Energiya 8 (1), 54–56.
         Kirillov, P.L., 1962. The summary of experimental data on heat transfer in liquid metals.
             Atomnaya Energiya 13, 481–484.
         Kirillov, P.L., Ushakov, P.A., 2001. Heat transfer to liquid metals: specific features, methods of
             investigation, and main relationships. Therm. Eng. 48 (1), 50–59.
         Rehme, K., 1973a. Simple method of predicting friction factors of turbulent flow in non-circular
             channels. Int. J. Heat Mass Transf. 16, 933.
         Rehme, K., 1973b. Pressure drop correlations for fuel element spacers, Nucl. Technol. Vol. 17,
             pp. 15–23, 1973.
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