International Journal of Materials Science

P-ISSN: 2707-8221, E-ISSN: 2707-823X
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2022, Vol. 3, Issue 1, Part A

Galena with B4C high density heavy concrete for shielding nuclear reactors


Author(s): Rasoul Mehrnejad, Abdulhalik Karabulut, Turgay Korkut and Bunyamin Aygun

Abstract: Shielding of biological type belong to nuclear reactor is considered as one of the main issues and lower complexity and expense of these installations is of important interest. In this paper, Galena mineral and Boron Carbide (B4C) were used to produce a high density heavy concrete. Galena minerals that present in the most regions of Iran were regarded to be applied in the concrete mix design. Boron Carbide (B4C) is regarded as a ceramic material that is efficient in order to absorb thermal neutron as a consequence of wide neutron absorption cross section. Neutron shielding characteristics of samples could explain the cross section in matter and neutron capture. Neutron cross section measurements of samples have done by using a source of 14.1MeV neutrons. By using Geant 4 Monte Carlo code, cross section and neutron capture of each samples could be calculated through it. As a consequence, cross section value of concrete can be raise by growing boron carbide (B4C) concentration and lower neutron capture value of samples and boost the attributes of shielding.

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How to cite this article:
Rasoul Mehrnejad, Abdulhalik Karabulut, Turgay Korkut, Bunyamin Aygun. Galena with B4C high density heavy concrete for shielding nuclear reactors. Int J Mater Sci 2022;3(1):01-04.
International Journal of Materials Science

International Journal of Materials Science

International Journal of Materials Science
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