https://doi.org/10.1140/epjp/s13360-024-05804-w
Regular Article
Impact of adding bismuth oxide nanoparticles functionalized with graphene oxide nanosheet on the polyvinyl chloride shielding properties
1
Nuclear Law and Nuclear Licenses Department, Nuclear, and Radiological Safety Research Centre, Egyptian Atomic Energy Authority, Cairo, Egypt
2
Safety Fuel Cycle Department, Nuclear and Radiological Safety Research Centre (NRSRC), Egyptian Atomic Energy Authority, Cairo, Egypt
3
Material Science and Nanotechnology Department, Faculty of Postgraduate Studies for Advanced Sciences (PSAS), Beni-Suef University, Beni-Suef, Egypt
Received:
7
September
2024
Accepted:
5
November
2024
Published online:
29
November
2024
This study investigates the enhancement of polyvinyl chloride (PVC) by incorporating Bi2O3-GO nanocomposites. We produced nanocomposites with varying concentrations (1, 2.5, 5, and 10 wt%). The prepared samples were characterized using scanning electron microscopy (SEM) and Fourier transform infrared spectroscopy (FTIR). X-ray diffraction (XRD) and thermogravimetric analysis (TGA) were also used. As well as the shielding effectiveness against ultraviolet rays and gamma radiation from 137Cs and ⁶⁰Co sources at energies of 662, 1173, and 1275 keV. Results indicate that the addition of Bi2O3-GO significantly improves the thermal stability of PVC, as evidenced by higher decomposition temperatures from TGA. The absorption coefficient increases, while energy gap values decrease with increased nanofiller weight concentrations. The linear attenuation coefficient (LAC) also rises with increasing nanofiller content and decreases with higher gamma-ray energies. Results were consistent with Phy-X software simulations. The sample with 10% wt of Bi2O3-GO composite demonstrated a highly fast neutron removal cross section (FNRC) and reduced mean free path (MFP). This indicates strong potential for use as a safe, environmentally friendly alternative to lead-based shielding materials. These PVC/Bi2O3-GO nanocomposites could be effectively utilized in radiation barriers and protective screens in settings involving neutron and low-energy gamma radiation, such as in radiography and radioactive material management.
© The Author(s) 2024
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