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Title

Gamma-Ray and Fast Neutron Shielding Parameters of Two New Titanium-Based Bulk Metallic Glasses

Year: 1400
COI: JR_IJMP-18-2_009
Language: EnglishView: 73
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Authors

Oyeleke Olarinoye - Department of Physics, Federal University of Technology Minna, Nigeria
Celestine Oche - Department of Physics, Federal University of Technology Minna, Nigeria

Abstract:

Introduction: Low-density bulk metallic glass (BMG) with good structural characteristics has the potential of being used for structural radiation shielding purposes. This study was conducted on two new low-density titanium (Ti)-based BMGs (i.e., Ti۳۲.۸Zr۳۰.۲Ni۵.۳Cu۹Be۲۲.۷ and Ti۳۱.۹Zr۳۳.۴Fe۴Cu۸.۷Be۲۲) to investigate their photon and fast neutron shielding capacities. Material and Methods: The mass attenuation coefficients, half-value layers, effective atomic numbers, and exposure buildup factors of the two BMGs were calculated at the photon energy values of ۱۵ keV and ۱۵ MeV. Computation of mass attenuation coefficients and effective atomic numbers was accomplished using the XCOM and auto-Zeff software, respectively. In addition, the geometric progression procedure-based computer code EXABCal was used for calculating the exposure buildup factors of BMG. The fast neutron removal cross-sections were also calculated for the two BMGs. The calculated photon and fast neutron shielding parameters for BMGs were compared with those of lead (Pb), heavy concrete, and some recently developed glass shielding materials and then analyzed according to their elemental compositions. Results: The results showed that though Pb had a better photon shielding capacity, Ti-BMG attenuated photons better than heavy concrete. Furthermore, BMG had a higher neutron removal cross-section, compared to heavy concrete and some recently developed glass shielding materials. The neutron removal cross-sections of Ti۳۲.۸Zr۳۰.۲Ni۵.۳Cu۹Be۲۲.۷ and Ti۳۱.۹Zr۳۳.۴Fe۴Cu۸.۷Be۲۲ were obtained as ۰.۱۶۶۳ and ۰.۱۶۴۵ cm-۱,respectively. Conclusion: his study revealed that Ti-based BMG with high strength and low density have potential applications in high-radiation environments, particularly in nuclear engineering for source and structural shielding.

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Paper COI Code

This Paper COI Code is JR_IJMP-18-2_009. Also You can use the following address to link to this article. This link is permanent and is used as an article registration confirmation in the Civilica reference:

https://civilica.com/doc/1187000/

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If you want to refer to this Paper in your research work, you can simply use the following phrase in the resources section:
Olarinoye, Oyeleke and Oche, Celestine,1400,Gamma-Ray and Fast Neutron Shielding Parameters of Two New Titanium-Based Bulk Metallic Glasses,https://civilica.com/doc/1187000

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