MYO.23.003
Neutron radiation is utilized in many applications such as nuclear therapy, nuclear power plants, material analysis, space research, and more. Neutron leaks can occur in these applications, posing hazards to staff, operators, and therapy patients. Therefore, effective neutron shielding materials are always needed. In this study, two new types of neutron shielding alloy materials were developed, consisting of aluminum, nickel, chromium, tungsten, boron carbide, manganese, molybdenum, and silicium. The chemical composition and weight ratios of the composites were determined using the Monte Carlo Simulation’s GEANT4 code. Mixing and molding methods were employed in the production of the alloys. Important neutron shielding parameters, such as the effective removal cross-section, half-value layer, mean free path, and radiation protection efficiency, were theoretically determined using the GEANT4 code. Additionally, fast neutron absorption capacities were measured using an Am-Be fast neutron source and a BF3 portable neutron detector. The results were compared with 316 LN stainless steel. All new alloy samples were determined to have better fast neutron shielding capabilities than these reference samples. It was also observed that the new alloy samples exhibit both high-temperature resistance and mechanical durability. It is suggested that these new alloy samples can be used in neutron radiation shielding applications such as nuclear reactors, radioactive waste storage, and nuclear shelters.
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Scientific and Technological Research Council of Ağrı İbrahim Çeçen University (BAP)
MYO.23.003
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Primary Language | English |
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Subjects | Material Physics, Nuclear Physics |
Journal Section | makaleler |
Authors | |
Project Number | MYO.23.003 |
Early Pub Date | December 28, 2024 |
Publication Date | December 31, 2024 |
Submission Date | November 6, 2024 |
Acceptance Date | December 23, 2024 |
Published in Issue | Year 2024 Volume: 10 Issue: 2 |