Abstract
To address the capability of passive decay heat removal systems of an advanced liquid-metal-cooled nuclear reactor, natural circulation experiments were performed to investigate the bouyancy-driven backflow phenomenon in the mixed convection flow of a cooling channel. In the AQUARIUS half-slab test facility, the core is represented by a vertical channel formed by two parallel electrically heated walls. At the top end, the channel is connected to an upper plenum where the fluid is cooled by an immersion cooler. Fluid velocities and temperatures were measured under quasi-steady-state laminar conditions. The experiments indicate that for low heat flux densities and large channel widths, cold water from the upper plenum flows down and penetrates the heated channel where the flow direction is upward. A comparison of analytical predictions using the COMMIX-2(V) three-dimensional computer code against experimental AQUARIUS data shows reasonable overall agreement. The numerical results reflect that backflow effects were not predicted for the investigated problem.
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