https://doi.org/10.1140/epjp/s13360-026-07513-y
Regular Article
Study of the gamma and neutron shielding properties of boron carbide-coated stainless steels
1
Ispir Hamza Polat Vocational School, Department of Electricity and Energy, Atatürk University, 25240, Erzurum, Turkey
2
Department of Physics, Faculty of Science, Atatürk University, Erzurum, Turkey
3
Department of Motor Vehicles and Transportation Technologies, Horasan Vocational School, Atatürk University, Erzurum, Turkey
a This email address is being protected from spambots. You need JavaScript enabled to view it.
, This email address is being protected from spambots. You need JavaScript enabled to view it.
Received:
17
October
2025
Accepted:
28
February
2026
Published online:
9
March
2026
Abstract
This study examined the gamma and neutron radiation shielding performance of AISI 304, 310, 316L, and 430 stainless steels, which were coated with boron carbide using the radio frequency magnetron sputtering technique. Coating durations were varied (7, 12, and 14 h) to determine optimal film growth conditions. Structural, morphological, and compositional analyses of the coatings were conducted using energy-dispersive X-ray (EDX), X-ray diffraction (XRD), and scanning electron microscope (SEM) techniques. Gamma attenuation properties were evaluated both theoretically, using WinXCom software, and experimentally via narrow-beam transmission measurements using 241Am, 133Ba, and 137Cs radioactive sources. Key shielding parameters, including mass attenuation coefficient, effective atomic number (Zeff), effective electron density (Neff), half-value layer, and mean free path were calculated. Neutron shielding effectiveness was experimentally assessed using a 241Am-Be neutron source and theoretically evaluated using MRCsC software. Results showed that B4C coatings improved neutron absorption by 4% to 12%, with AISI 316L and 304 exhibiting the highest macroscopic removal cross sections. The findings demonstrate that B4C coatings significantly enhance the radiation shielding performance of stainless steels without compromising their mechanical integrity, offering a viable, lead-free solution for nuclear and medical radiation protection applications.
© The Author(s) 2026
Open Access This article is licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons licence, and indicate if changes were made. The images or other third party material in this article are included in the article's Creative Commons licence, unless indicated otherwise in a credit line to the material. If material is not included in the article's Creative Commons licence and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this licence, visit http://creativecommons.org/licenses/by/4.0/.

