Gamma-ray interaction studies of concrete with waste glass fillers.

IF 0.8 4区 环境科学与生态学 Q4 ENVIRONMENTAL SCIENCES Radiation protection dosimetry Pub Date : 2024-07-17 DOI:10.1093/rpd/ncae109
Ashwitha Chikkegowda, Lingaraj Adarsh Raj, Sankarshan Belur Mohan, Sannathammegowda Krishnaveni
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Abstract

In the present work, the efficacy of waste glass as fillers in concrete for gamma-ray shielding has been studied. Glass fillers of 0, 15, 30, 45, and 60% concentrations have been incorporated into the concrete mixture. The attenuation measurements were performed using gamma spectrometer with NaI(Tl) detector at 511, 662, 1173, and 1332 keV gamma energies. Gamma-ray shielding parameters, such as the mass attenuation coefficient (μ/ρ), are determined for all filler concentrations. The mass attenuation coefficient of the prepared samples was found to be varied from 0.081 to 0.088, 0.071 to 0.088, 0.05 to 0.058, and 0.05 to 0.055 (cm2 per g) for 511, 662, 1173, and 1332 keV gamma energies, respectively. It was observed that experimentally determined (μ/ρ) values were in very good agreement with theoretical values calculated from EDAX data. Furthermore, it was observed that (μ/ρ) showed an increasing trend with an increase in filler concentration, which is attributed to the increase in the shielding property of the material. Therefore, the glass-concrete composite can be accustomed to reduce the intensity of gamma radiation.

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混凝土与废玻璃填料的伽马射线相互作用研究。
在本研究中,我们研究了废玻璃作为混凝土填料对伽马射线屏蔽的功效。在混凝土混合物中分别加入了浓度为 0、15、30、45 和 60% 的玻璃填料。在 511、662、1173 和 1332 千伏伽马能量下,使用带有 NaI(Tl)探测器的伽马能谱仪进行了衰减测量。确定了所有填料浓度的伽马射线屏蔽参数,如质量衰减系数(μ/ρ)。在 511、662、1173 和 1332 千伏伽马能量下,制备的样品的质量衰减系数分别为 0.081 至 0.088、0.071 至 0.088、0.05 至 0.058 和 0.05 至 0.055(cm2/g)。实验结果表明,实验测定的 (μ/ρ) 值与根据 EDAX 数据计算出的理论值非常吻合。此外,还观察到 (μ/ρ) 随着填料浓度的增加而呈上升趋势,这归因于材料屏蔽性能的提高。因此,玻璃-混凝土复合材料可用于降低伽马辐射强度。
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来源期刊
Radiation protection dosimetry
Radiation protection dosimetry 环境科学-公共卫生、环境卫生与职业卫生
CiteScore
1.40
自引率
10.00%
发文量
223
审稿时长
6-12 weeks
期刊介绍: Radiation Protection Dosimetry covers all aspects of personal and environmental dosimetry and monitoring, for both ionising and non-ionising radiations. This includes biological aspects, physical concepts, biophysical dosimetry, external and internal personal dosimetry and monitoring, environmental and workplace monitoring, accident dosimetry, and dosimetry related to the protection of patients. Particular emphasis is placed on papers covering the fundamentals of dosimetry; units, radiation quantities and conversion factors. Papers covering archaeological dating are included only if the fundamental measurement method or technique, such as thermoluminescence, has direct application to personal dosimetry measurements. Papers covering the dosimetric aspects of radon or other naturally occurring radioactive materials and low level radiation are included. Animal experiments and ecological sample measurements are not included unless there is a significant relevant content reason.
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