Computational fluid dynamic simulations of heat transfer from a 2?2 wire-wrapped fuel rod bundle to supercritical pressure water

[+] Author and Article Information
Krishna Podila

Canadian Nuclear Laboratories, Chalk River, Ontario, Canada, K0J 1P0

Yanfei Rao

Canadian Nuclear Laboratories, Chalk River, Ontario, Canada, K0J 1P0

1Corresponding author.

ASME doi:10.1115/1.4037747 History: Received April 03, 2017; Revised August 21, 2017


Within the Generation-IV International Forum, Canadian Nuclear Laboratories (CNL) led the conceptual fuel bundle design effort for the Canadian supercritical water cooled reactor (SCWR). The proposed fuel rod assembly for the Canadian SCWR design comprised of 64-elements with spacing between elements maintained using the wire-wrap spacers. Experimental data and correlations are not available for the fuel-assembly concept of the Canadian SCWR. To analyze the thermalhydraulic performance of the new bundle design, CNL is using computational fluid dynamics (CFD) as well as the subchannel approach. Simulations of wire-wrapped bundles can benefit from the increased fidelity and resolution of a CFD approach due to its ability to resolve the boundary layer phenomena. Prior to the application, the CFD tool has been assessed against experimental heat transfer data obtained with bundle subassemblies to identify the appropriate turbulence model to use in the analyses. In the present paper, assessment of CFD predictions was made with the wire-wrapped bundle experiments performed at Xi'an Jiaotong University in China. A 3D CFD study of the fluid flow and heat transfer at supercritical pressures for the rod bundle geometries was performed with the key parameter being the fuel rod wall temperature. It was found that the CFD simulation tends to overpredict the fuel wall temperature, and the predicted location of peak temperature differs from the measurement by up to 65 degrees.

Copyright (c) 2017 by ASME
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