Monte Carlo simulations reveal the impact of duct geometry on buildup factor and flux, indicating significant applications in neutron transport.
The analysis of neutron transport through ducts holds significant importance due to its applicability in numerous practical scenarios, particularly in systems involving complex duct geometries. The presence of these ducts is inevitable in several nuclear installations. In this work, we have developed a simulation program based on the Monte Carlo method that has been validated by the MCNPX calculation code. We have also introduced a new concept of buildup factor in order to study the effect of the geometry of the double legged duct on the buildup factor and the flux at the duct exit.
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Z. Faik Ouahab (2025) studied this question.
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