Development of appropriate mixes of Self-compacting concrete (SCC) for neutron shielding

Pai, B.H.V (2015) Development of appropriate mixes of Self-compacting concrete (SCC) for neutron shielding. Phd. Thesis thesis, Manipal Institute of Technology, Manipal.

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Radiation shield is a physical entity placed between a source of ionizing radiation and an object to be protected in order to reduce the radiation level at the position of the object. Proper shielding of the radiation facilities is mandatory to provide a safe environment both to the living and non-living world. Of all the radiation shielding materials employed, concrete is considered to be the most economical and effective for neutrons and gamma. Normal density and high density concretes of adequate thickness are used to effectively contain radiation. In recent times, research in the field of developing low activation concrete shield has been a thrust area in most countries. In India it has been a continued endeavour of researchers to constantly look for shielding materials that would not only extend the operational life of nuclear installations, but also result in reduction of radioactive wastes for handling and disposal during the decommissioning operation. Structures built to contain radiation at nuclear installations are designed with higher factors of safety to resist seismic loads. This design consideration can yield higher percentages of steel, leading to possible congestion of reinforcement at the member junctions. The use of mechanical vibrators for compacting the concrete mix in such situations may not be possible. This situation can be effectively tackled with the use of Self-compacting concrete (SCC). As the name suggests, self-compacting concrete is a type of concrete that is capable of flowing and consolidating into the structural formwork all by itself.

Item Type: Thesis (Phd. Thesis)
Subjects: Engineering > MIT Manipal > Civil Engineering
Depositing User: MIT Library
Date Deposited: 17 Jun 2017 08:57
Last Modified: 17 Jun 2017 08:57

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