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DC Field | Value | Language |
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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 |
Appears in Collections: | Department of Chemistry |
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