Investigation of Thermal Neutron Radiation Shielding Features of B2O3 and Gd2O3-doped Materials (Quartz, Glasses, Al, W) by Using MCNP6.2
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Pre-published on:
November 27, 2022
Published on:
June 15, 2023
Abstract
In this study, thermal and fast neutron energies of total macroscopic cross sections of quartz and some elements (like Al, W) doped with Gd2O3 were calculated by using the (MCNP6) Monte Carlo Simulation Code. Furthermore, the macroscopic effective removal cross-section of fast neutrons was calculated theoretically for the selected materials and doped materials. In the results obtained from the calculations, it was seen that total macroscopic cross-section values were better in Gd2O3-added materials. In addition, it has been observed that the selected materials have the highest fast neutron total cross section with the contribution of Gd2O3. The results of this study provide a good understanding of the shielding properties of Quartz, and some elements like Al and W doped with Gd2O3 against thermal and fast neutrons.
DOI: https://doi.org/10.22323/1.414.1192
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Copyright owned by the author(s) under the term of the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.
Copyright owned by the author(s) under the term of the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.