Radiation Physics and Engineering
A peer-reviewed journal published by K. N. Toosi University of Technology

Lithium borohydride (LiBH4): An innovative material for neutron radiation shielding

Document Type : Research Article

Authors

Mohammadreza Lotfalian
Mitra Athari Allaf
Masoud Mansouri

Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran

https://doi.org/10.22034/rpe.2024.462728.1198
Abstract
Radiation shielding plays a crucial role in various industries, including nuclear and space exploration. Among the most abundant elements and isotopes found in nature, B-10 has one of the highest neutron absorption cross-sections, closely followed by Li-6. It is worth noting that hydrogen, with its light nucleus, serves as an excellent neutron reflector. Surprisingly, the potential of the lithium borohydride molecule (LiBH4), which consists exclusively of these elements, as a shield against neutron radiation has not yet been explored. This study investigates various materials that can potentially be used as shields. First, we assessed traditional shields and previous optimizations for shielding. The findings showed that concrete containing 10% B4C yielded the best results. High-performance concrete (HPC) replaced regular concrete. By gradually incorporating lithium borohydride into the shield, along with the appropriate level of boron carbide, further optimization was achieved. Calculations were performed using the MCNPX 2.7E code. The introduction of the new shield resulted in a significant 40% reduction in volume compared with the previous sample. The study findings showed that a 30 cm thick shield effectively blocked 95% of the total neutrons and 92% of the total gamma radiation. Additionally, it was noted that the shielding effects of lithium borohydride against fast neutrons are greater than those of boron carbide. Various parameters and data of the designed shield were calculated and compared with those of the previous sample.

Highlights

  • The inclusion of lithium borohydride resulted in an enhancement of shield efficiency.
  • The performance of lithium borohydride surpassed that of boron carbide in terms of effectiveness against fast neutrons.
  • Recent calculations of the shielding data were conducted and compared with earlier shield configurations.
  • The longevity of the engineered shield is deemed adequate for its intended application.

Keywords

High performance concrete
MCNPX code
Radioactive protection
MET 1000 reactor, Lithium borohydride, Neutron radiation shielding
Alabsy, M. T. and Elzaher, M. A. (2023). Radiation shielding performance of metal oxides/EPDM rubber composites using Geant4 simulation and computational study. Scientific Reports, 13(1):7744.
Alipour, M., Saadi, M. K., and Rohani, A. A. (2019). Investigation on Concrete Neutron Shielding Properties Filled by B4C, CdO, and BN Microparticles. Moscow University Physics Bulletin, 74:608–613.
Bostelmann, F., Holcomb, A. M., Clarity, J. B., et al. (2019). Nuclear Data and Benchmarking Program: Nuclear Data Performance Assessment for Advanced Reactors. Technical report, Oak Ridge National Lab (ORNL), Oak Ridge, TN (United States).
Busch, R. D., Briesmeister, J. F., Forster, R. A., et al. (2009). Criticality Calculations with MCNP5 TM: A Primer.
Cai, Y., Hu, H., Pan, Z., et al. (2018). Metaheuristic optimization in shielding design for neutrons and gamma rays reducing dose equivalent as much as possible. Annals of Nuclear Energy, 120:27–34.
Delkowski, M., Smith, C. T., Anguita, J. V., et al. (2023). Radiation and electrostatic resistance for ultra-stable polymer composites reinforced with carbon fibers. Science Advances, 9(11):eadd6947.
Devarajan, Y. (2024). Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production. Kerntechnik, 89(3):368–381.
Elsafi, M., Almousa, N., Al-Harbi, N., et al. (2023). Ecofriendly and radiation shielding properties of newly developed epoxy with waste marble and WO3 nanoparticles. Journal of Materials Research and Technology, 22:269–277.
Gholamzadeh, Z., Ebrahimzadeh, R., Choopan Dastjerdi, M. H., et al. (2024). Assessment of shielding performance of NBR through simulation and experiments at MNSR beam line. Radiation Physics and Engineering.
Gulbicim, H., Aksu, M., Turkan, N., et al. (2023). Gamma ray shielding properties of synthesized lanthanide borides using EGSnrc code. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 542:259–269.
Gur, A., Artig, B., and Cakir, T. (2017). Photon attenuation properties of concretes containing magnetite and limonite ores. Physicochemical Problems of Mineral Processing, 53.
Han, Y. and Zhou, T. (2023). Performance analysis of high-performance concrete materials in civil construction. Materials, 16(16):5711.
Kerr, R. A. (2013). Radiation will make astronauts’ trip to Mars even riskier.
Konobeyev, A. Y., Fischer, U., Pereslavtsev, P., et al. (2019). Evaluated data files for neutron irradiation of W-182 and W-186 at energies up to 200 MeV. Karlsruher Institut für Technologie (KIT).
Laiblová, L., Peˇ sta, J., Kumar, A., et al. (2019). Environmental impact of textile reinforced concrete facades compared to conventional solutionsLCA case study. Materials, 12(19):3194.
Lotfalian, M., Athari Allaf, M., and Mansouri, M. (2024). Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor. Kerntechnik, 89(4):383–399.
Moadab, N. H. and Saadi, M. K. (2019). Optimization of an Am-Be neutron source shield design by advanced materials using MCNP code. Radiation Physics and Chemistry, 158:109–114.
Mokhtari, K., Saadi, M. K., Ahmadpanahi, H., et al. (2021a). Fabrication, characterization, simulation and experimental studies of the ordinary concrete reinforced with micro and nano lead oxide particles against gamma radiation. Nuclear Engineering and Technology, 53(9):3051–3057.
Mokhtari, K., Saadi, M. K., Panahi, H. A., et al. (2021b). The shielding properties of the ordinary concrete reinforced with innovative nano polymer particles containing PbO–H3BO3 for dual protection against gamma and neutron radiations. Radiation Physics and Chemistry, 189:109711.
Okabe, R., Xue, S., Vavrek, J. R., et al. (2024). Tetris-inspired detector with neural network for radiation mapping. Nature Communications, 15(1):3061.
Öztürk, O., Karabur¸ c, S ¸. N., Saydan, M., et al. (2022). High rate X-ray radiation shielding ability of cement-based composites incorporating strontium sulfate (SrSO4) minerals. Kerntechnik, 87(1):115–124.
Reda, S. (2016). Gamma ray shielding by a new combination of aluminum, iron, copper and lead using MCNP5. Arab Journal of Nuclear Sciences and Applications, 49(4):211–217.
Salimi, M., Ghal-Eh, N., and Amirabadi, E. A. (2018). Characterization of a new shielding rubber for use in neutron-gamma mixed fields. Nuclear Science and Techniques, 29:1–8.
Scott, S. R. and Shafer, M. M. (2020). A new method for measurement of lithium isotopes with nuclear applications. Progress in Nuclear Energy, 120:103234.
Shamsinasab, M., Asgari, M., and Eshghi, M. (2024). Investigation and simulation of gamma-neutron shielding for nuclear-pumped lasers. Radiation Physics and Engineering, 5(1):41–47.
Shao, Q., Zhu, Q., Wang, Y., et al. (2024). Development and application analysis of high-energy neutron radiation shielding materials from tungsten boron polyethylene. Nuclear Engineering and Technology, 56(6):2153–2162.
Stankovi´ c, S. J., Ilic, R., Jankovi´ c, K. S., et al. (2010). Gamma radiation absorption characteristics of concrete with components of different type materials. Acta Physica Polonica A, 117(5):812–816.
Stauff, N., Kim, T., Taiwo, T., et al. (2016). Benchmark for neutronic analysis of sodium-cooled fast reactor cores with various fuel types and core sizes. Technical report, Organisation for Economic Co-Operation and Development.
Takasaki, I., Nagumo, T., Inaba, T., et al. (2012). Measurement of the isotopic abundance of boron-10 by inductively coupled plasma-quadrupole mass spectrometry. Journal of Nuclear Science and Technology, 49(8):867–872.
Tekin, H. O., Singh, V. P., and Manici, T. (2017). Effects of micro-sized and nano-sized WO3 on mass attenauation coefficients of concrete by using MCNPX code. Applied Radiation and Isotopes, 121:122–125.
Xie, W., Dhinojwala, A., Gianneschi, N. C., et al. (2024). Interactions of Melanin with Electromagnetic Radiation: From Fundamentals to Applications. Chemical Reviews.
Yorgun, N. Y., Kavaz, E., Tekin, H., et al. (2019). Borax effect on gamma and neutron shielding features of lithium borate glasses: an experimental and Monte Carlo studies. Materials Research Express, 6(11):115217.
Radiation Physics and Engineering
Volume 6, Issue 1
Winter 2025
Pages 9-20

  • Receive Date 13 June 2024
  • Revise Date 28 August 2024
  • Accept Date 07 September 2024

Home

Submit Manuscript

Reviewers

Contact Us