Study of the Effect of Boron Carbide Content in Concrete as Radiation Shielding Application

Mohd Reusmaazran Yusof; Yusof Abdullah; Zaifol Samsu

doi:10.4028/www.scientific.net/AMR.535-537.1877

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HomeAdvanced Materials ResearchAdvanced Materials Research Vols. 535-537Study of the Effect of Boron Carbide Content in...

Study of the Effect of Boron Carbide Content in Concrete as Radiation Shielding Application

Abstract:

Keywords: Boron carbide, concrete, shielding, neutron, attenuation. Abstract. Boron carbide (B4C) is a ceramic material which is effectively absorb thermal neutron due to wide neutron absorption cross section. In this work, B4C is added into concrete as fine aggregates to test the attenuation properties by getting the attenuation coefficient of the concrete/ B4C. The samples of concrete/ B4C were exposing to the thermal neutron radiation source (241-Americium-Berylium) at the dose rate of 29.08 mR/h. The result show that the attenuation coefficient of the sample with 20wt% B4C is 0.299 cm-1 and the sample without B4C is 0.238 cm-1 and hence, concrete/ B4C is suitable as a shielded for thermal neutron radiation.

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Periodical:

Advanced Materials Research (Volumes 535-537)

Pages:

1877-1880

DOI:

https://doi.org/10.4028/www.scientific.net/AMR.535-537.1877

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Online since:

June 2012

Authors:

Mohd Reusmaazran Yusof, Yusof Abdullah, Zaifol Samsu

Keywords:

Attenuation, Boron Carbide, Concrete, Neutron, Shielding

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