Abstarct: Nowadays, nuclear reactor miniaturization and dimension reduction play a crucial role in achieving agility and efficiency. The material Zr3Si2 is considered a special choice due to its high temperature resistance, suitable reflectivity, and density. The MCNPX code is an advanced computational tool utilized for simulating and analyzing the interaction of radiation with various materials. This code can be employed to investigate the properties and performance of different substances. In this thesis, the neutron interaction with Zr3Si2 has been simulated using the MCNPX code. Subsequently, a comparison has been made by simulating the neutron reflection coefficient of Zr3Si2 and several other reflector samples at energy levels of 600KeV and 1.2MeV, using the results obtained from the MCNPX code, while varying the thickness. By contrasting the neutron reflection coefficient graphs of different materials and validating the calculations, it can be inferred that Zr3Si2, as a neutron reflector, can play a significant role in nuclear reactor shielding and miniaturization.