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Influence of waste glass on the gamma-ray shielding performance of concrete.
- Source :
-
Annals of Nuclear Energy . Jan2025, Vol. 210, pN.PAG-N.PAG. 1p. - Publication Year :
- 2025
-
Abstract
- • Radiation shielding abilities of concrete which is good in environmental protection. • Recycling and reusing of waste glass in a useful way addresses waste management. • The use of waste glass as additive, which solved the material selection problem. • Solution to problem of finding optimal composition to for best shielding in concrete. • Solution to problem of identifying most efficient shielding material composition. • Use of local materials align with aim of SDG, addressing environmental sustainability. In this work, the local low-cost materials from Nigeria were companied together to produce a lead-free concrete that can be used in shielding the ionizing γ-rays. This work investigated the impacts of partially replacing coarse aggregates (crushed granite) with a crushed waste glass on the chemical, physical, and radiation shielding characteristics. The developed concretes' density was measured experimentally, and the fabricated concretes' elemental chemical composition was determined utilizing a Thermo-Scientific X-ray fluorescence connected to an ARL-QUANT'X-EDXRF-Analyzer. The increase in the waste glass/granite (WG/G) substitution ratio between 0 and 17.6 % decreases the density of the produced concrete from 2.4 g/cm3 to 2.33 g/cm3. On the other hand, the absorption per unit mass (MAC) of the produced concretes increased by raising the WG/G ratio, where there was a 0.217–0.247 cm2/g increase in the MAC at 0.081 MeV, by raising the WG/G ratio between 0 and 17.6 %. Simultaneously, the study shows that the radiation protection efficiency (RPE) at 2.506 MeV for a 10 cm thickness of the fabricated concrete reaches 53.49, 61.14, 54.98, and 55.29 % for concretes with WG/G content of 0.0, 5.3, 11.1, and 17.6 % with the same order, respectively. Therefore, the thicker thicknesses of the developed concretes can offer high shielding capacity to be applied in radiation protection applications. [ABSTRACT FROM AUTHOR]
Details
- Language :
- English
- ISSN :
- 03064549
- Volume :
- 210
- Database :
- Academic Search Index
- Journal :
- Annals of Nuclear Energy
- Publication Type :
- Academic Journal
- Accession number :
- 179556111
- Full Text :
- https://doi.org/10.1016/j.anucene.2024.110876