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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.