A comprehensive study on matrix material choices for glass fiber–reinforced composites used in gamma and neutron radiation protection


Özdemir H., Yılmaz M., Erkoyuncu İ., İspir T., AYDIN S. Ş., Akman F.

Radiation Physics and Chemistry, cilt.246, 2026 (SCI-Expanded, Scopus) identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 246
  • Basım Tarihi: 2026
  • Doi Numarası: 10.1016/j.radphyschem.2026.113929
  • Dergi Adı: Radiation Physics and Chemistry
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus, Chemical Abstracts Core, Chimica, Compendex, EMBASE, INSPEC
  • Anahtar Kelimeler: FLUKA, GEANT4, Glass fibers, Secondary radiation, WinXCOM
  • Atatürk Üniversitesi Adresli: Evet

Özet

The need for safe, lightweight, environmentally friendly and economical shielding materials to reduce radiation-induced health risks is increasing. In this context, glass-based composites, especially glass fibers, have become one of the most striking options in recent years. Glass fiber materials offer a new approach in shielding technologies thanks to their low density, high mechanical strength, thermal stability and flexible production possibilities. In this study, the produced secondary radiation and the shielding efficiencies of gamma and neutron radiations for selected glass fibers investigated. The basic shielding parameters of glass fiber materials coded as E-Glass, D-Glass, S-Glass, and EGR-Glass were determined for 16 photon energies ranging from 0.060 MeV to 2.614 MeV, as well as for neutron energies of 0.025 eV, 0.4 eV, 100 eV, and 4.5 MeV. The half-value layer (HVL), linear and mass attenuation coefficients (μ and μ/ρ), effective atomic number (Zeff), and radiation protection efficiency (RPE) were obtained using the GEANT4 and FLUKA simulation codes in addition to theoretical calculations in order to evaluate the glass fiber composites' capacity to shield against gamma radiation. The GEANT4 and FLUKA simulation programs were used to determine the mean free path (MFP), total macroscopic cross-section (ΣT) and number of transmitted neutrons in order to assess the neutron shielding capabilities of glass fiber samples. The μ results of the studied glass fibers in the photon energy range of 0.060 to 2.614 MeV were found to vary between 0.845 and 0.082 cm−1, while the ΣT results varied between 6.7616 and 2.0322 cm−1 in the neutron energy range of 0.025 eV to 4.5 MeV. Using the GEANT4 simulation code, secondary radiation which are crucial for radiation safety were additionally determined while analyzing the shielding capacity of glass fibers. The glass fiber coded as EGR-Glass demonstrated the best gamma radiation shielding performance among all samples, and it also showed enhanced neutron shielding capability compared to the other glass fibers.