A numerical study of turbulent upward flow of super critical water in a 2×2 rod bundle with non-uniform heating

Abstract

This work is part of a benchmarking excise organized by IAEA CRP in SCWR thermal-hydraulics aimed at improving the understanding and prediction accuracy of the thermal-hydraulic phenomena relevant to SCWRs. An experiment carried out using a 2x2 SCWR bundle at University of Wisconsin-Madison was modeled using an open-source Computational Fluid Dynamics (CFD) code - Code_Saturne. The k-w SST model was employed to account for the buoyancy-aided turbulent flow in the fuel channel. Significant heat transfer deterioration (HTD) was observed in the boundary layer, which is commonly expected to occur in buoyancy-aided flows. For comparison, simulations were also conducted using ANSYS FLUENT with similar model setups.

Metadata

Authors/Creators:

Liu, B.
He, S. https://orcid.org/0000-0003-0326-2447
Moulinec, C.
Uribe, J.C.

© 2020 by ASME. This is an author produced version of a paper subsequently published in Journal of Nuclear Engineering and Radiation Science. Uploaded in accordance with the publisher's self-archiving policy. Article available under the terms of the CC-BY licence (https://creativecommons.org/licenses/by/4.0/).

Dates: