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Benchmarking of three different CFD codes in simulating natural, forced, and mixed convection flows
Publikationstyp
Journal Article
Date Issued
2015-06-15
Sprache
English
Author(s)
Journal
Volume
67
Issue
12
Start Page
1324
End Page
1351
Citation
Numerical Heat Transfer, Part A 67 (12): 1324-1351 (2015)
Publisher DOI
Scopus ID
Publisher
Taylor & Francis
In this study, three different CFD codes are assessed in simulating two distinct flow problems with heat transfer. The first case consists of an ascending forced and mixed convection flow, a representative flow in the core of gas-cooled nuclear reactors under "post-trip" conditions, and the second case involves natural convection in an enclosed tall cavity that represents the gas-filled cavities around the nuclear reactor cores. Computations are conducted using the standard k-ω-SST model and the nonlinear k-ε model of Suga. Overall, the results were in satisfactory agreement, and, therefore, the present study represents a successful benchmarking exercise for the nuclear community.
DDC Class
600: Technology