Comprehensive evaluation of Gd2O3 reinforced polyhydroxybutyrate as a hybrid neutron–gamma shielding material: Spatial dose mapping, photon buildup factors and neutron capture performance under primary and secondary radiation
Applied Radiation and Isotopes, cilt.236, 2026 (SCI-Expanded, Scopus)
- Yayın Türü: Makale / Tam Makale
- Cilt numarası: 236
- Basım Tarihi: 2026
- Doi Numarası: 10.1016/j.apradiso.2026.112769
- Dergi Adı: Applied Radiation and Isotopes
- Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus, Chemical Abstracts Core, Chimica, Compendex, EMBASE, INSPEC, MEDLINE, Academic Search Ultimate (EBSCO), Engineering Source (EBSCO)
- Anahtar Kelimeler: Fluka, Gadolinium oxide, Geant4, Polyhydroxybutyrate, Radiation shielding, Total ionizing dose
- Erciyes Üniversitesi Adresli: Evet
Özet
In this study, the shielding properties of biodegradable polyhydroxybutyrate composites reinforced with various amounts of gadolinium oxide, ranging from 0 wt% to 25 wt%, against photon and neutron radiation are investigated theoretically using Monte Carlo simulation codes (Geant4 and FLUKA), as well as theoretical software packages (WinXCom and Phy-X). The dosimetric parameters, such as exposure build-up factors, energy absorption build-up factors, and suppression of secondary photon build-up, are computed up to 40 mean free paths, indicating that the addition of gadolinium oxide effectively reduces the build-up of secondary photons within the matrix material. The addition of gadolinium oxide significantly enhances the photon shielding properties, especially for low-energy photons ranging from 50–60 keV. In addition, 60 keV and 600 keV 2D total ionizing dose distributions indicate that the penetration of photons is restricted within the near-surface region of the composite material. The shielding properties of the composite material against neutrons indicate that there is a possibility of lateral diffusion of neutrons, whereas the composite material reinforced with 25 wt% of gadolinium oxide exhibited 99.9% efficiency for the capture of thermal neutrons, which effectively reduces the production of secondary gamma rays due to neutron capture reactions.