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Radiation Shielding Concrete with alternate constituents: An approach to address multiple hazards

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dc.contributor.author Singhal, Anupam
dc.contributor.author Routroy, Srikanta
dc.contributor.author Bhunia, Dipendu
dc.contributor.author Lahoti, Mukund
dc.date.accessioned 2021-11-11T11:27:01Z
dc.date.available 2021-11-11T11:27:01Z
dc.date.issued 2021-02-15
dc.identifier.uri https://www.sciencedirect.com/science/article/pii/S0304389420321919?via%3Dihub
dc.identifier.uri http://dspace.bits-pilani.ac.in:8080/xmlui/handle/123456789/3541
dc.description.abstract Radiation Shielding Concrete (RSC) is a superior alternative to many conventional and modern shields against gamma and neutron radiation hazards. The present work is the first comprehensive review on utilization of alternate materials, emphasizing hazardous industrial byproducts, as constituents of RSC. Such usage enhances the performance, sustainability, and affordability of RSC. Added advantages are the immobilization of wastes and the conservation of natural resources for RSC. The review analyses incorporation of ferrous and non-ferrous slags, mines wastes, plastics, red mud, cathode ray tube's glass, metallic wastes, fly ash, silica fume, and miscellaneous residues. Besides, utilization of fibers, nanoparticles, and calcined clay is investigated. The influence on shielding efficiency is adjudged by scrutinizing changes in parameters such as half-value layer and linear attenuation coefficients. Similarly, variations in mechanical and durability properties are investigated and compared. The underlying responsible factors related to the physical, chemical and morphological characteristics of materials and their consequences on RSC’s behavior are correlated. In association with alternatives, the advantages, disadvantages, and possible treatment methods are discussed. The country-wise, material-specific, and progressive research trends are revealed to facilitate future work in this upcoming field. Finally, conclusions are drawn with exposition of current bottlenecks and scope of future research. en_US
dc.language.iso en en_US
dc.publisher Elsiever en_US
dc.subject Civil Engineering en_US
dc.subject Gamma and neutron rays en_US
dc.subject Attenuation en_US
dc.subject Hazardous wastes en_US
dc.subject Sustainability en_US
dc.subject Mechanical Engieering en_US
dc.title Radiation Shielding Concrete with alternate constituents: An approach to address multiple hazards en_US
dc.type Article en_US


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