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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2022.4
- 수록면
- 1,456 - 1,463 (8page)
- DOI
- https://doi.org/10.1016/j.net.2021.10.007
이용수
초록· 키워드
오류제보하기
The aim of this work is to study the radiation shielding properties of cement samples with waste glassincortated into its composition. The mass attenuation coefficient (MAC) of the samples were experimentally determined to evaluate their radiation shielding ability. The experimental coefficient wasevaluated using NaI detector for gamma energies between 59.53 keV and 1408.01 keV using differentradioactive point sources Am-241, Eu-152, Co-60, and Cs-137, and the gamma transmission parametershalf-value layer, mean free path, and transmission factor were calculated. The theoretical coefficient ofthe composites was determined using Geant4 and XCOM software. The results were also comparedagainst Geant4 and XCOM simulations by calculating the relative deviation between the values todetermine the accuracy of the results. In addition the mechanical properties (including Compressive andporosity) as well as the thermogravimetric analysis were tested for the present samples. Overall, it wasconcluded that the cement sample with 50% waste glass has the greatest shielding potential for radiationshielding applications and is a useful way to reuse waste glass.
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