Monte Carlo simulation on shielding properties of neutron-gamma from 252Cf source for Alumino-Boro-Silicate glasses

Abstract

Neutron-gamma attenuation characteristics of the Alumino-Boro-Silicate (ABS) glasses were estimated based on MCNPX simulation and theoretical calculations. The watt fission distribution was used to extract the neutron spectrum and the obtained results were reported in the presence and absence of the glass sample. The other attenuation parameters such as effective removal cross section (ΣR), mass removal cross section (∑Rρ), Half Value Thickness (HVT), Tenth Value Thickness (TVT), and also mean free path (mfp) were also demonstrated. The received data depicts that glass coded ABS-0 is an appropriate material in terms of neutron attenuation purposes in comparison to the other selected shielding materials. Moreover, it can be figured out that the increment of the Bi2O3 rate decreases the neutron shielding ability of the Alumino-Boro-Silicate glass and has a negative effect on the fast neutron shielding proficiency. Besides, using Doppler Effect gamma spectrum for spontaneous fission 252Cf source were extracted in shielding materials, and data represented graphically. Linear attenuation coefficient(μ), HVT, mfp for a wide energy range of incident gamma rays were also estimated. The simulated results showed that the ABS-4 glass sample possesses the highest μ value (better gamma shielding efficiency) which varies in the range between 0.381763 and 0.954323 cm−1 while the lowest μ value is obtained for ABS-0 that varies in the range between 0.339447 and 0.511594 cm−1.