Jul 6 – 13, 2022
Bologna, Italy
Europe/Rome timezone

Investigation of Thermal Neutron Radiation Shielding Features of B2O3 and Gd2O3-doped Materials (Quartz, Glasses, Al, W) by Using MCNP6.2

Jul 8, 2022, 7:05 PM
1h 25m
Bologna, Italy

Bologna, Italy

Palazzo della Cultura e dei Congressi
Poster Detectors for Future Facilities, R&D, novel techniques Poster Session

Speaker

Mirac Kamislioglu (Bandırma Onyedi Eylül University)

Description

In this study, the total macroscopic cross sections of thermal and fast neutron interactions with quartz, glass, and some elements such as Al, W, stainless steel doped with B2O3 and Gd2O3 were computed by using Monte Carlo N-Particle Code (MCNP6.2). Also, the macroscopic effective removal cross-sections of fast neutron interactions were theoretically calculated based on the mass removal cross-section values for various elements in materials and additives. The results show that the highest value for both thermal neutron total macroscopic cross-section and fast neutron total macroscopic cross-section were obtained with Gd2O3 doped glass. Besides, Gd2O3 doping gives the highest fast neutron total macroscopic cross-section among all additives. The results of this study provide a good understanding of the shielding properties of Quartz, glass, and some other elements such as Al, W, stainless steel, doped with B2O3 and Gd2O3 for thermal and fast neutrons.

In-person participation No

Primary authors

Ayşe BAT (Erciyes University) Dr Emrah Tiras Mirac Kamislioglu (Bandırma Onyedi Eylül University)

Presentation materials