Page 268 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
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238 Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
Fig. 6.1.1.7 Snapshots of the instantaneous streamwise velocity component and temperature
fields, and their fluctuations for various Pr values.
Fig. 6.1.1.8 Instantaneous temperature field in a flow over a backward-facing step with the
heated wall under the step.
Very few works are found in the literature for the fuel bundle flow simulations con-
cerning low Prandtl number fluids, such as liquid metals (Govindha Rasu et al., 2014).
A first attempt at carrying out DNSs of fully developed, buoyancy-induced convection
flows around a vertical rod bundle is done by Angeli and Stalio (2018). Finite volume
computations are performed by an original, second-order accurate discretization tech-
nique based on the representation of arbitrarily shaped cylindrical boundaries on a