Simulation of a hypothetical pwr fuel element with 316 steel cladding doped with graphene

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. Graphene are investigated as promising additives due to their 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 evaluate its performance. The results highlight that the inclusion of graphene 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 graphene s as additives to enhance nuclear fuel performance, promoting safer, more efficient, and sustainable nuclear energy.