Keshmiri, AmirAmirKeshmiriUribe, JuanJuanUribeShokri, NimaNimaShokri2021-10-282021-10-282015-06-15Numerical Heat Transfer; Part A: Applications 67 (12): 1324-1351 (2015-06-15)http://hdl.handle.net/11420/10676In 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.en1040-778220151213241351Journal Article10.1080/10407782.2014.965115Other