Abstract

This study aimed to perform an investigation for the potential implementation of bismuth silicate glasses as novel shield equipment instead of ordinary shields in nuclear medicine facilities. Accordingly, a group of Bi2O3 reinforced silicate glass system were investigated and compared with ordinary shields in terms of their gamma-ray attenuation properties in diagnostic nuclear medicine radioisotope energies emitted from 99mTc, 111In, 67Ga, 123I, 131I, 81mKr, 201Tl, 133Xe. Mass attenuation coefficient results for glass samples were calculated comparatively with the XCOM program and MCNPX code. The gamma-ray attenuation parameters such as half value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Zeff) were obtained in the diagnostic gamma ray energy range from 75 to 336 keV. To confirm the attenuation performance of superior sample, obtained results were extensively compared with ordinary shielding materials. According to the results obtained, BISI6 glass sample with the highest Bi2O3 additive has an excellent gamma-ray protection.

Highlights

  • In this study, which was based on literature studies, 6 bismuth silicate glass samples were envisioned according to their Bi2 O3 content within the range of 20–70% mole and were tested for their attenuation against diagnostic energy in nuclear medicine for the purposes of shielding effectiveness

  • Chemical composition, elemental compositions, and density (ρ) of glass samples can be obtained from Table 1

  • The results showed that BISI6 sample has higher half value layer (HVL) values than Pb but lower than ordinary concrete (OC), hematite-serpentine concrete (HSC), and scrap concrete (SCC) [37]

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Summary

Introduction

Unlike the radiation technologists of diagnostic radiology, it is worth mentioning that there is another stakeholder such as isotope technician and isotope technologist in nuclear medicine facilities This is often beneficial for isotope experts to use a ring dosimeter on one or both hands in addition to standard safety equipment if they have high rates of activity to control. This allows workers to monitor radiation doses while working with highly radioactive materials in a safe manner. In this study, which was based on literature studies, 6 bismuth silicate glass samples were envisioned according to their Bi2 O3 content within the range of 20–70% mole and were tested for their attenuation against diagnostic energy in nuclear medicine for the purposes of shielding effectiveness. The results of this large-focused study would have great significance for research on a new generation of radiation-shielding glass shields and their advanced development

Materials and Methods
Method of Calculating Radiation Absorption Parameters
Monte Carlo Simulations
Results and Discussion
Conclusions
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