Exploring gamma-ray and neutron attenuation properties of some high-density alloy samples through MCNP Monte Carlo code
DOI:
https://doi.org/10.22399/ijcesen.422Keywords:
Alloy Compositions, Shielding Parameters, Phy-X/PSD, MCNPXAbstract
Effective radiation shielding is critical across various sectors, including nuclear power generation and medical applications. This study evaluates the radiation attenuation properties of seven distinct alloy samples: 316 Stainless Steel, Zircaloy-4, Monel 400, Alloy 625, Titanium Grade-5 (Ti-6Al-4V), Niobium-Titanium (NbTi) Alloy, and Haynes 230. Using the MCNP Monte Carlo simulation code and the Phy-X/PSD software, the gamma and neutron shielding capacities of these alloys were systematically investigated. Among the alloys, Haynes 230 exhibited superior gamma radiation attenuation efficiency. Furthermore, the Fast Neutron Removal Cross Section (FNRCS) values indicated that Haynes 230 (0.16375 1/cm) possessed comparable neutron shielding capabilities to 316 Stainless Steel (0.16758 1/cm) and Monel 400 (0.16818 1/cm), underscoring its robustness as a neutron shield. Although Monel 400 and 316 Stainless Steel demonstrated marginally better neutron shielding performance, Haynes 230 remains a formidable contender due to its balanced performance against both gamma and neutron radiation, making it a promising candidate for applications requiring comprehensive radiation protection. Moreover, the study demonstrated that Haynes 230 exhibited a significant advantage in terms of its linear attenuation coefficient, HVL, TVL, and mean free path (mfp) values, further solidifying its role as an efficient gamma-ray shield. Additionally, Monte Carlo simulations highlighted the superior transmission factor (TF) of Haynes 230, especially for thicker materials, positioning it as an ideal material for high-intensity radiation shielding applications.
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