Studying the effect of some additives to the borosilicate Glass on the neutron shielding properties
DOI:
https://doi.org/10.21123/bsj.2024.10609Keywords:
Fast neutron, Half-value layer, mean free path, Removal cross-section, Shielding material, Fast neutron, Half-value layer, mean free path, Removal cross-section, Shielding materialAbstract
The development of radiation shielding material is important since radioactive sources are used in industry, medicine, and agriculture. As a result, more research and development has been put into looking into different glass systems based on their unique qualities for protecting against neutron radiation. This study focuses on investigating glass-based materials for neutron shielding purposes. This investigation delves into the neutron shielding properties of a mixture comprising Sodium Aluminum borosilicate glass (SiB2Na2Al2O9)X, with added reinforcement materials (SiC)100-X, (TiB2)100-X, and (BiClO)100-X ( X=95, 80, 65, and 50%), the mixtures are denoted as codes G1, G2 and G3 respectively. Results and calculations indicate that adding reinforcing materials to borosilicate glass in various quantities enhances rapid neutron removal (∑R). An increased reinforcing material ratio reduces shielding half value layer (HVL) and mean free path (MFB)to neutron. Comparing theoretical results, adding titanium nitride (TiB2) as reinforcement to borosilicate glass yields the maximum neutron attenuation and the least HVL at X=50. Thus, the G2 shield is the best for neutron radiation protection.
Received 04/01/2024
Revised 22/03/2024
Accepted 24/03/2024
Published Online First 20/11/2024
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