An investigation into gamma radiation shielding parameters of the (Al:Si) and (Al+Na):Si-doped international simple glasses (ISG) used in nuclear waste management, deploying Phy-X/PSD and SRIM software

Nuclear power plants that produce sustainable energy are the most striking examples of generating carbon-free energy. However, nuclear demand safe management waste. The radiation tests materials, which used in successful waste plants, must be carried out. In this study, interaction parameters were examined International simple glasses (ISG) with superior properties, management. gamma shielding properties (Al:Si) and (Al?+?Na):Si-dopped ISG investigated using Photon Shielding Dosimetry (Phy-X / PSD) software for selected range. LAC, MAC, MFP, HVL, TVL, Zeff, Neff, Ceff Zeq, EBF, EABF FNRCS calculations applied to assess protection by Phy-X/PSD software. addition, MSP PR (H1, He+2) values calculated SRIM Also, each obtained parameter provided us so important information on protection, these methods have been frequently literature. Substituting an atomic fraction (Al?+?Na):Si resulted a reduction total cross-section glass, lowered MAC. results showed highest MAC value belong ISG-A00N glass. gradually decreased as Al, Na Si contents increased. Likewise, TVL MFP changed coherent this. Moreover, Zeff Neff seen sample take maximum other inversely. effective glass turned out at mean free path penetration values. Computations made SiO2, Al2O3, B2O3, Na2O, CaO ZrO2 content given ISG-C, ISG-A00, ISG-A12, ISG-A22, ISG-A00N, ISG-A11N, ISG-A18N ISG-A23N codes. When all evaluated, has Ca density was found best feature. It is also noteworthy does not contain any Al component. As investigation, it such small doped increases feature revealed ISG-A00N?>?ISG-A00?>?ISG-C?>?ISG-A12?>?ISG-A11N?>?ISG-A22?>?ISG-A18N?>?ISG-A23N samples, ascending order attenuators low radiations.