Heavy liquid metals are often considered as coolant fluids for fast nuclear reactors because of their physical and neutronic properties. Nevertheless, these fluids are not well known as ordinary fluids, such as air or water, and the use of reliable numerical tools for the simulation of turbulent heat transfer inside reactor cores refrigerated with liquid metals is still an open issue. In the present work we propose the use of a k-e-kt-et turbulence model to improve the prediction of turbulent heat transfer for liquid metal flows in triangular rod bundle geometry with different pitch-to-diameter ratios and different Peclet numbers. Nusselt number comparisons between experimental correlations and different heat turbulence models are reported for many test cases.

Manservisi S., Menghini F (2014). Triangular rod bundle simulations of a CFD-turbulence model for heavy liquid metals k-e-kt-et heat transfer. NUCLEAR ENGINEERING AND DESIGN, 273, 251-270 [10.1016/j.nucengdes.2014.03.022].

Triangular rod bundle simulations of a CFD-turbulence model for heavy liquid metals k-e-kt-et heat transfer

MANSERVISI, SANDRO;
2014

Abstract

Heavy liquid metals are often considered as coolant fluids for fast nuclear reactors because of their physical and neutronic properties. Nevertheless, these fluids are not well known as ordinary fluids, such as air or water, and the use of reliable numerical tools for the simulation of turbulent heat transfer inside reactor cores refrigerated with liquid metals is still an open issue. In the present work we propose the use of a k-e-kt-et turbulence model to improve the prediction of turbulent heat transfer for liquid metal flows in triangular rod bundle geometry with different pitch-to-diameter ratios and different Peclet numbers. Nusselt number comparisons between experimental correlations and different heat turbulence models are reported for many test cases.
2014
Manservisi S., Menghini F (2014). Triangular rod bundle simulations of a CFD-turbulence model for heavy liquid metals k-e-kt-et heat transfer. NUCLEAR ENGINEERING AND DESIGN, 273, 251-270 [10.1016/j.nucengdes.2014.03.022].
Manservisi S.; Menghini F
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11585/308316
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