Analysis of the benchmark problem for the 7th meeting of the IAHR working group on advanced nuclear reactors thermal hydraulics with multi-dimensional code AQUA.

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For the purpose of the participation to a benchmark exercise of the 7th Meeting of the International Association for Hydraulic Research (IAHR) Working Group on Advanced Nuclear Reactors Thermal Hydraulics, which is to be held in Kernforschungszentrum Karlsruhe GmbH, FRG, August 27-29, 1991, two experimental cases of the benchmark problems were calculated using a combined method of higher-order accurate schemes and the Algebraic Stress turbulence Model (ASM) of a multi-dimensional themohydraulic analysis code AQUA developed at PNC. From the analyses, the following analytical results have been obtained: (1)Penetration phenomena at the inlet channel observed in experiments were predicted well with the combined method. (2)Axial distributions of temperature and horizontal velocity components in the test plenum agreed with experiments.