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thermal-hydraulic study of the lbe-cooled fuel assembly in the myrrha reactor: experiments and simulations

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For many cutting-edge systems based on fast neutrons, heavy liquid metals (HLMs), such as lead-bismuth eutectic (LBE) and pure lead, are popular candidate coolants.

LBE is employed, in instance, in Mol (Belgiumgroundbreaking )'s MYRRHA fast reactor, which can run in either critical mode or as a sub-critical accelerator-driven system. Key thermal-hydraulic features of these systems, such as the proper cooling of fuel components, must be evaluated with a heavy emphasis on safety.

This flow scenario presents a challenge for computational fluid dynamics (CFD) models, such as those used to relate the turbulent transport of momentum and heat, due to the complicated geometry and low Prandtl number of the LBE (Pr 0.025). Therefore, accurate experimental information is required for validation.

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