Investigation of Borated Polyethylene as a Neutron Shielding Material using Monte Carlo Simulation Code
DOI:
https://doi.org/10.70882/josrar.2024.v1i1.1Keywords:
Neutron shielding, borated polyethylene, FLUKA simulation, Monte Carlo method, Eco-friendly materialsAbstract
The use of neutron shielding materials is essential in nuclear reactors to ensure safety and minimize radiation exposure. Conventional materials like lead and concrete pose environmental concerns, leading to the need for more sustainable alternatives. In this study, we have investigated the usage of borated polyethylene as an eco-friendly neutron shielding material using the Monte Carlo simulation code, FLUKA. Borated polyethylene slabs of varying thicknesses were evaluated for neutron attenuation, focusing on key parameters such as mass attenuation coefficient, mean free path, and half-value layer (HVL). Simulation results showed that borated polyethylene achieved a mass attenuation coefficient of 0.150 cm²/g at 0.025 MeV, which is 25% higher than that of conventional concrete. The mean free path for thermal neutrons was 6.67 cm, while the half-value layer was 3.34 cm, indicating effective neutron shielding, especially for thermal neutrons. Increased material thickness led to significant reductions in neutron fluence and transmission, with neutron fluence reduced to 5.0E+5 n/cm² at 15 cm thickness. These findings suggest that borated polyethylene is highly effective in attenuating neutron radiation and offers a more sustainable alternative to traditional materials.
References
Abdelgawad, K. (2023). Using eco-friendly glass from rice straw ash as a shield for cosmic rays. Bulletin of Faculty of Science, Zagazig University, 2023(3), 66–76. https://doi.org/10.21608/bfszu.2023.185066.1240
Alhassan, U., Joseph, E., & Abubakar, I. (2024). Investigation of the Specific Activity of Al-0.1%Au Wire for Epithermal Neutron Activation Analysis for Nirr-1 After Conversion from Heu to Leu. International Journal of Research and Scientific Innovation, XI(II), 478–486. https://doi.org/10.51244/ijrsi.2024.1102037
Aliyu Haruna Sani, & Musa Amanabo. (2021). Lead: A concise review of its toxicity, mechanism and health effect. GSC Biological and Pharmaceutical Sciences, 15(1), 055–062. https://doi.org/10.30574/gscbps.2021.15.1.0096
Almisned, G., Susoy, G., & Tekin, H. O. (2024). Neutron transmission analysis in borated polyethylene, boron carbide, and polyethylene: Insights from MCNP6 simulations. Radiation Physics and Chemistry, 218(November 2023), 111585. https://doi.org/10.1016/j.radphyschem.2024.111585
Ashezua, J. A., Joseph, E., & Asuku, A. (2024). Estimation of the Thermal Power of Nigeria Research Reactor-1 Low Enriched Uranium Core at Half Power using the Heat Balance Approach. Nigerian Journal of Theoretical and Environmental Physics, 2(1), 78–85. https://doi.org/10.62292/njptep.v2i1.2024.33
Battistoni, G., Bauer, J., Boehlen, T. T., Cerutti, F., Chin, M. P. W., Dos Santos Augusto, R., Ferrari, A., Ortega, P. G., Kozlowska, W., Magro, G., Mairani, A., Parodi, K., Sala, P. R., Schoofs, P., Tessonnier, T., & Vlachoudis, V. (2016). The FLUKA code: An accurate simulation tool for particle therapy. Frontiers in Oncology, 6(MAY). https://doi.org/10.3389/fonc.2016.00116
Bawazeer, O., Makkawi, K., Aga, Z. B., Albakri, H., Assiri, N., Althagafy, K., & Ajlouni, A. W. (2023). A review on using nanocomposites as shielding materials against ionizing radiation. Journal of Umm Al-Qura University for Applied Sciences, 9(3), 325–340. https://doi.org/10.1007/s43994-023-00042-9
Chen, Y. Q., & Yan, B. H. (2023). The technology of shielding design for nuclear reactor: A review. Progress in Nuclear Energy, 161(November 2022), 104741. https://doi.org/10.1016/j.pnucene.2023.104741
Fu, X., Ji, Z., Lin, W., Yu, Y., & Wu, T. (2021). The Advancement of Neutron Shielding Materials for the Storage of Spent Nuclear Fuel. Science and Technology of Nuclear Installations, 2021. https://doi.org/10.1155/2021/5541047
Hadiza Gambo Rimi, Emmanuel Joseph, Dimas Skam Joseph, & Dlama Zira Joseph. (2023). Evaluation of shielding thickness in the radio-diagnostic facility of Turai Yaradua Maternity and Children Hospital Katsina, Katsina State, Nigeria. International Journal of Science and Research Archive, 9(2), 156–162. https://doi.org/10.30574/ijsra.2023.9.2.0529
Joseph, Nasiru, R., Sadiq, U., & Ahmed. (2015). The use of k 0 – NAA Standardization Technique in evaluating elements of significance for plant growth in the cultivated areas of Dutsin-Ma Local Government, Katsina State-Nigeria. IOSR Journal of Applied Physics, 7(5), 49–59. https://doi.org/10.9790/4861-07514959
Kamoru, L., & Joseph, E. (2023). The study of shielding design parameter (thickness) in two health tertiary institutions in Katsina Metropolis, Nigeria. Dutse Journal of Pure and Applied Sciences, 9(3a), 281–288. https://doi.org/10.4314/dujopas.v9i3a.28
Knoll, G. F. (2005). Radiation Detection and Measurement (Hardcover). In John Wiley & Sons, Inc. (pp. 1–816).
Malvin H. Kalos, P. A. W., & Monte. (2009). Monte Carlo Methods Second. In John Wiley & Sons.
Mkhaiber, A. F., & Dawood, S. K. (2019). Calculation of Shielding Parameters of Fast Neutrons for Some Composite Materials. Al-Mustansiriyah Journal of Science, 30(1), 210–215. https://doi.org/10.23851/mjs.v30i1.520
Sala, P. R. (2007). The FLUKA code : description and benchmarking. May, 31–49.
Tanabashi, M., Hagiwara, K., Hikasa, K., Nakamura, K., Sumino, Y., Takahashi, F., Tanaka, J., Agashe, K., Aielli, G., Amsler, C., Antonelli, M., Asner, D. M., Baer, H., Banerjee, S., Barnett, R. M., Basaglia, T., Bauer, C. W., Beatty, J. J., Belousov, V. I., … Schaffner, P. (2018). Review of Particle Physics. Physical Review D, 98(3), 30001. https://doi.org/10.1103/PhysRevD.98.030001
Tyagi, G., Singhal, A., Routroy, S., Bhunia, D., & Lahoti, M. (2021). Radiation Shielding Concrete with alternate constituents: An approach to address multiple hazards. Journal of Hazardous Materials, 404, 124201. https://doi.org/10.1016/j.jhazmat.2020.124201
Uddin, Z., Yasin, T., Shafiq, M., Raza, A., & Zahur, A. (2020). On the physical, chemical, and neutron shielding properties of polyethylene/boron carbide composites. Radiation Physics and Chemistry, 166(November 2018), 1–8. https://doi.org/10.1016/j.radphyschem.2019.108450
Wang, K., Ma, L., Yang, C., Bian, Z., Zhang, D., Cui, S., Wang, M., Chen, Z., & Li, X. (2023). Recent Progress in Gd-Containing Materials for Neutron Shielding Applications: A Review. Materials, 16(12). https://doi.org/10.3390/ma16124305
Yasin, T., & Khan, M. N. (2008). High density polyethylene/boron carbide composites for neutron shielding. E-Polymers, April 2008. https://doi.org/10.1515/epoly.2008.8.1.670
Downloads
Published
Issue
Section
License
Copyright (c) 2024 Journal of Science Research and Reviews
This work is licensed under a Creative Commons Attribution-NonCommercial 4.0 International License.
- Attribution — You must give appropriate credit, provide a link to the license, and indicate if changes were made. You may do so in any reasonable manner, but not in any way that suggests the licensor endorses you or your use.
- NonCommercial — You may not use the material for commercial purposes.
- No additional restrictions — You may not apply legal terms or technological measures that legally restrict others from doing anything the license permits.
