Abstract
In the present work, bismuth borate glass samples with the composition of (99-x) B2O3 + 1Cr2O3 + (x) Bi2O3 (x = 0, 5, 10, 15, 20, and 25 wt %) were prepared using the melt quenching technique. The mass attenuation coefficient (MAC) of the prepared glass samples was measured through a narrow beam technique using a NaI(Tl) scintillation detector. Four point sources were used (241Am, 133Ba, 152Eu, and 137Cs) to measure the MAC for the prepared glasses. The experimental data were compared with the theoretical results obtained from the XCOM, and it was shown that for all samples at all tested energies, the relative deviation between the samples is less than 3%. This finding signifies that the experimental data can adequately be used to evaluate the shielding ability of the glasses. The MAC of the sample with x = 25 wt % was compared with different lead borate glasses and the results indicated that the present sample has high attenuation which is very close to commercial lead borate glasses. We determined the transmission factor (TF), and found that it is small at low energies and increases as the energy increases. The addition of Bi2O3 leads to reduction in the TF values, which improves the shielding performance of the glass system. The half value layer (HVL) of the BCrBi-10 sample was 0.400 cm at 0.595 MeV, 1.619 cm at 0.2447 MeV, and 4.946 cm at 1.4080 MeV. Meanwhile, the HVL of the BCrBi-20 sample is equal to 0.171 and 4.334 cm at 0.0595 and 1.4080 MeV, respectively. The HVL data emphasize that higher energy photons tend to penetrate through the glasses with greater ease than lower energy photons. Furthermore, the fast neutron removable cross section (FNRC) was determined for the present samples and compared with lead borate glass and concrete, and the results showed a remarkable superiority of the bismuth borate glass samples.
Highlights
IntroductionThese means should take into account the dose of radiation that the population may be exposed to in the event of a nuclear accident
The scientific trend towards replacing fossil fuels by generating energy from nuclear reactors, and the accompanying possibilities of radioactive leakage and dangerous radioactive waste, which pose great risks to humans, requires serious research and effective means of protection and shielding [1,2]. These means should take into account the dose of radiation that the population may be exposed to in the event of a nuclear accident. This protection can be achieved through the use of effective shields, which requires the studying of the characteristics of potential shielding materials, such as mechanical properties, characteristics of different radiation attenuation, expected energies, cost and availability of materials, ease of production, effectiveness, and the likelihood of low cost
Another critical property is the extent of the shielding material’s resistance to damage that may be caused as a result of exposure to ionizing radiation, in addition to making sure that those shields are not toxic
Summary
These means should take into account the dose of radiation that the population may be exposed to in the event of a nuclear accident This protection can be achieved through the use of effective shields, which requires the studying of the characteristics of potential shielding materials, such as mechanical properties, characteristics of different radiation attenuation, expected energies, cost and availability of materials, ease of production, effectiveness, and the likelihood of low cost. Another critical property is the extent of the shielding material’s resistance to damage that may be caused as a result of exposure to ionizing radiation, in addition to making sure that those shields are not toxic. The effects of radiation on the optical and mechanical features of the shielding material must be minimal [3]
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