FLUKA Monte Carlo Assessment of Fe₂B-Based Shielding Materials for Secondary Neutrons in a 1000 MeV Proton Accelerator
DOI:
https://doi.org/10.22399/ijcesen.4544Keywords:
Neutron shielding, FLUKA, Dose distribution, FerroboronAbstract
High-energy proton accelerators generate high-energy neutrons through spallation processes, and these neutrons represent one of the most challenging particle types in terms of radiation shielding. In this study, secondary neutron dose distributions in the tunnel air environment at different distances and within the surrounding shielding structures were calculated for a 1000 MeV proton accelerator using FLUKA Monte Carlo simulations. Standard concrete, ferroboron (Fe₂B), and concrete doped with 20% Fe₂B were considered as shielding materials, and their shielding performances at various thicknesses were comparatively evaluated. The simulation results demonstrate that Fe₂B provides superior shielding performance compared to standard concrete and 20% Fe₂B-doped concrete, owing to its high effectiveness in moderating fast neutrons and absorbing thermal neutrons. In addition, an increase in shielding thickness was found to significantly reduce the measured dose levels. The findings indicate that Fe₂B-based materials constitute an effective and viable alternative for optimized shielding design in high-energy proton accelerator facilities
References
[1] Sariyer, D., & Küçer, R. (2020). Effect of different materials to concrete as neutron shielding application. Acta Physica Polonica A, 137(4, Special Issue: ICCESEN-2019), 477–480. https://doi.org/10.12693/APhysPolA.137.477
[2] Emikönel, S., & Akkurt, İ. (2025). Radiation shielding properties of B₂O₃–Bi₂O₃ glass. International Journal of Computational and Experimental Science and Engineering (IJCESEN), 11(2). https://doi.org/10.22399/ijcesen.2157
[3] Soyal, H., & Sarıhan, M. (2025). Evaluation of radiation protection knowledge and attitudes of health services vocational school students participating in practice in radiated environments. International Journal of Computational and Experimental Science and Engineering (IJCESEN), 11(2). https://doi.org/10.22399/ijcesen.508
[4] Liu, J. (2005). Nuclear reactions: Spallation physics and ADS target design. Brazilian Journal of Physics, 35(3B), 894–902. https://doi.org/10.1590/S0103-97332005000500048
[5] Sarıyer, D. (2017). Proton hızlandırıcılarında tünel tasarımı için kullanılan farklı zırh maddelerinin doz dağılımlarına etkileri (Doktora tezi). Manisa Celal Bayar Üniversitesi, Fen Bilimleri Enstitüsü, Manisa, Türkiye.
[6] Sarkar, P. K. (2010). Neutron dosimetry in the particle accelerator environment. Radiation Measurements, 45(10), 1476–1483. https://doi.org/10.1016/j.radmeas.2010.07.001
[7] Paul, M. B., Dutta Ankan, A., Deb, H., & Ahasan, M. M. (2023). A Monte Carlo simulation model to determine the effective concrete materials for fast neutron shielding. Radiation Physics and Chemistry, 202, 110476. https://doi.org/10.1016/j.radphyschem.2022.110476
[8] Waheed, F., Al-Sudani, M. A. M., & Akkurt, I. (2025). The experimental enhancing of the radiation shield properties of some produced compounds. International Journal of Applied Sciences and Radiation Research (IJASRaR), 2(1). https://doi.org/10.22399/ijasrar.1
[9] Sarıyer, D., Küçer, R., & Küçer, N. (2015). Neutron shielding properties of concrete and ferro-boron. Acta Physica Polonica A, 128(2-B), B-201. https://doi.org/10.12693/APhysPolA.128.B-201
[10] Sarıyer, D., Küçer, R., & Küçer, N. (2015). Neutron shielding properties of concretes containing boron carbide and ferro-boron. Procedia – Social and Behavioral Sciences, 195, 1752–1756. https://doi.org/10.1016/j.sbspro.2015.06.320
[11] Sariyer, D., & Küçer, R. (2018). Development of neutron shielding concrete containing iron content materials. AIP Conference Proceedings, 1935(1), 100003. https://doi.org/10.1063/1.5025991
[12] Barbhuiya, S., Das, B. B., Norman, P., & Qureshi, T. (2024). A comprehensive review of radiation shielding concrete: Properties, design, evaluation, and applications. Structural Concrete. https://doi.org/10.1002/suco.202400519
[13] Gharieb, M., Mosleh, Y. A., Alwetaishi, M., Hussein, E. E., & Sultan, M. E. (2021). Effect of using heavy aggregates on the high performance concrete used in nuclear facilities. Construction and Building Materials, 310, 125111. https://doi.org/10.1016/j.conbuildmat.2021.125111
[14] Rokni, S. H., Cossairt, J. D., & Liu, J. C. (2007). Radiation shielding at high-energy electron and proton accelerators (SLAC Report). Stanford Linear Accelerator Center.
[15]Hançerlioğulları, A. (2006). Monte Carlo simulation method and the MCNP code system. Kastamonu Education Journal, 14(2), 545–556.
[16]Günoğlu, K., & Akkurt, İskender. (2023). Gamma-ray attenuation properties carbide compounds (WC, Mo2C, TiC, SiC, B4C) using Phy-X/PSD software. International Journal of Applied Sciences and Radiation Research , 1(1), 1–8. https://doi.org/10.22399/ijasrar.6
[17]Waheed, F., Mohamed Abdulhusein Mohsin Al-Sudani, & Iskender Akkurt. (2025). The Experimental Enhancing of the Radiation Shield Properties of Some Produced Compounds. International Journal of Applied Sciences and Radiation Research , 2(1). https://doi.org/10.22399/ijasrar.1
[18]Vural, M., Kabaca, A., Aksoy, S. H., Demir, M., Karaçam, S. Çavdar, Ulusoy, İdil, … Günay, O. (2025). Determination Of Radiation Dose Levels to Which Partois And Spinal Cord (C1-C2) Regions Are Exposed In Computed Tomography Brain Imaging. International Journal of Applied Sciences and Radiation Research , 2(1). https://doi.org/10.22399/ijasrar.17
[19]Morad Kh. Hamad. (2025). Synergistic Evaluation of Ionizing Radiation Shielding in Novel Lead-Free Alloys Using Geant4 MC toolkit. International Journal of Applied Sciences and Radiation Research , 2(1). https://doi.org/10.22399/ijasrar.47
Downloads
Published
How to Cite
Issue
Section
License
Copyright (c) 2025 International Journal of Computational and Experimental Science and Engineering

This work is licensed under a Creative Commons Attribution 4.0 International License.