Effect of Increasing Weight of SiC Ceramic on Radiation Shielding of Al 2219

Year 2024, Volume: 12 Issue: 4, 1155 - 1163, 31.12.2024

Kubilay Akgül , Berkay Çakır , Seda Gürgen Avşar , Zübeyde Özkan , Uğur Gökmen

https://doi.org/10.29109/gujsc.1582890

Abstract

Artificial radiation has many disadvantages as well as benefits. In order to eliminate or minimize these disadvantages and to be an alternative to radiation shield materials used, Al 2219 alloy material, Al 2219+% 5 SiC, Al 2219+% 10 SiC, Al 2219+% 15 SiC metal matrix composite material's mass attenuation coefficient (MAC), mean free path (MFP), linear attenuation coefficient (LAC), half value layer (HVL), fast neutron cross section (FNRC) and tenth value layer (TVL) parameters were analyzed in Phy-x/PSD program. Powder grain structure of Al 2219 and SiC powders were analyzed by scanning electron microscope (SEM) and powder grain size analysis was performed by Malvern Mastersizer 3000 device. As a result of the analysis of fast neutron and gamma radiations, linear attenuation values of the material against photons increased depending on the increasing reinforcement ratio, while HVL, TVL and MFP values decreased. The FNRC values of Al 2219 alloy material, Al 2219+5% SiC, Al 2219+10% SiC, Al 2219+15% SiC materials were calculated as 0.081 cm-1, 0.083 cm-1, 0.084 cm-1 and 0.084 cm-1, respectively.

Keywords

Al 2219, SiC, Phy-x/PSD, radiation shielding

Supporting Institution

GAZİ BAP

Project Number

FKA-2023-8617

Thanks

The researchers would like to thank Gazi University Scientific Research Projects Office, TURKEY (Project Number: FKA-2023-8617), YÖK 100/2000 and TUBITAK 2211-C Programs for their financial support.

SiC Seramiğin Artan Ağırlığının Al 2219'un Radyasyon Zırhlamasına Etkisi

Abstract

Project Number

FKA-2023-8617

References

• [1] Ali M. Onaizi, Mugahed Amran, Waiching Tang, Nour Betoush, Mohammad Alhassan, Raizal S.M. Rashid, Mohammad Fares Yasin, K.H. Bayagoob, Sagheer A. Onaizi, Radiation-shielding concrete: A review of materials, performance, and the impact of radiation on concrete properties, Journal of Building Engineering, Volume 97, 2024, 110800, ISSN 2352-7102.
• [2] M.A. Masoud, A.M. El-Khayatt, K.A. Mahmoud, Alaa M. Rashad, M.G. Shahien, Bottros R. Bakhit, A.M. Zayed, Valorization of hazardous chrysotile by H3BO3 incorporation to produce an innovative eco-friendly radiation shielding concrete: Implications on physico-mechanical, hydration, microstructural, and shielding properties, Cement and Concrete Composites, Volume 141, 2023, 105120, ISSN 0958-9465.
• [3] Kareman Ahmed, Hosam M. Gomaa, A.A. Bendary, S.S. Mohammad, H.A. Saudi, Structural and radiation shielding parameters of heavy metal-based environment-friendly glass systems for nuclear radiation security applications, Journal of Physics and Chemistry of Solids, Volume 181, 2023, 111526, ISSN 0022-3697.
• [4] M. Kamislioglu, Research on the effects of bismuth borate glass system on nuclear radiation shielding parameters, Results in Physics, Volume 22, 2021, 103844, ISSN 2211-3797.
• [5] Nassar N. Asemi, Saad Aldawood, Mohamad S. AlSalhi, Hamoud Kassim, Abdulraaof H. Al-Qaili, Aziz, A.A. Advancing gamma radiation shielding with Bitumen-WO₃ composite materials, Journal of Radiation Research and Applied Sciences, Volume 17, Issue 4, 2024, 101143, ISSN 1687-507.
• [6] Ozben, T. Kilickap, E. Cakır, O. Investigation of mechanical and machinability properties of SiC particle reinforced Al-MMC. J. Mater. Process. Technol. 2008, 198, 220–225.
• [7] Arık, H. Al-Si3N4Toz Metal Kompozit Malzeme Üretimi ve Aşınma Davranışının Araştırılması. GU J Sci, Part C, 7(4): 776-787(2019).
• [8] Hua, A., Su, Y., Cai, Y., Zhang, D., Ouyang, Q. Strengthened high-temperature resistance in B4C/SiC/2024Al composite via SiC nanowires pinning grain boundary. Journal of Alloys and Compounds 1000 (2024) 175046.
• [9] Lian, X., Xu, W., Zhang, P., Wang, W., Xie, L., Chen, X. Design and mechanical properties of SiC reinforced Gd2O3/6061Al neutron shielding composites. Ceramics International 49 (2023) 27707–27715.
• [10] Al-mugren, K.S., Almalki, L., Alshehri, R., Alamri, S., Almurayshid, M., Alsuhybani, M., Alharbi, R., Khandaker, M.U. Development of lead-free metal carbides and ceramic decorated HDPE composites for low energy X-ray shielding applications. Radiation Physics and Chemistry 220 (2024) 111688.
• [11] Uzun, S. Comprehensive analysis of nuclear clad materials: Neutronics, radiation shielding, and modal assessment. Nuclear Engineering and Design 428 (2024) 113510.
• [12] R. F. Muraca, J. S. Whittick. Materials Data Handbook Aluminum Alloy 2219 (2nd Edition)
• [13] Kılıçoğlu, O., & Tekin, H. O. Bioactive glasses with TiO2 additive: Behavior characterization against nuclear radiation and determination of buildup factors. Ceramics International, 46(8-Part A), 10779-10787.
• [14] Şakar, E., Özpolat, Ö.F., Alım, B., Sayyed, M.I., Kurudirek, M. Phy- X / PSD: Development of a user friendly online software for calculation of parameters relevant to radiation shielding and dosimetry.
• [15] Abdelmonem, A.M., Elshamndy, S.K., Ali, M.S. Studying of radiation attenuation and interaction parameters of some materials used in dental applications. Studying of radiation attenuation and interaction parameters of some materials used in dental applications. Nuclear Instruments and Methods in Physics Research B 558 (2025) 165575.
• [16] Yalçın, G., Özkan, Z., Gökmen, G., Ocak, S.B. Radiation Shielding Properties of Reinforced (BaSO4 and SiC) AZ91 Materials. Mechanical Engineering, Materials Science Research and Applications. Güven Plus Group Inc. Publications, 2022, pp.107-133.