In this study, the importance of simulations conducted in MCNP5 and the modifications implemented in 316 steel to optimize energy efficiency in nuclear power production are explored. Molybdenum (Mo) is investigated as a promising additive due to its low absorption cross-section for thermal neutrons, which facilitates a more significant participation of neutrons in fission and heat generation. Through the use of the MCNP5 code, simulations were conducted to analyze a hypothetical UO2 fuel element with different enrichment zones to assess its performance. The results highlight that the inclusion of molybdenum in the fuel cladding alloy has a significant impact on neutron production, suggesting that this addition may compromise energy generation efficiency. In summary, this study emphasizes the potential of molybdenum as an additive to enhance nuclear fuel performance, promoting safer, more efficient, and sustainable nuclear energy.
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Lopes et al. (2024) studied this question.
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