Preparation and radiation shielding features of high density, transparent borosilicate glasses with different Bi2O3 contents

Abstract

This work assessed highly effective bismuth borosilicate glasses' nuclear radiation shielding capabilities in terms of different concentrations of BiO. Melt-quenching was the method used to create the glasses. The Phy-X/PSD program was used to compute the μ values. The bismuth borosilicate glasses' nuclear radiation shielding properties were determined in the 0.015–15 MeV energy range. Increasing Bi₂O₃ concentration resulted in an increase in mass attenuation coefficient, linear attenuation coefficient, and effective atomic number. Conversely, the half value layer and mean free path values decreased. The B48Bi17 sample, with its largest Z, is a great gamma attenuator. The results of a new study may help to clarify the nature of the BiO additive used in borosilicate glasses, which are a potential form of shield for use in industrial and medical radiation facilities.