Aygun, BunyaminSakar, ErdemKarabulut, AbdulhalikAlim, BunyaminSayyed, Mohammed, ISingh, Vishwanath P.Yorgun, Nergiz Yildiz2024-10-042024-10-0420210033-82302193-3405https://doi.org/10.1515/ract-2020-0067http://hdl.handle.net/20.500.12403/3181In this study, the fast neutron and gamma-ray absorption capacities of the new glasses have been investigated, which are obtained by doping CoO,CdWO4,Bi2O3, Cr2O3, ZnO, LiF,B2O3 and PbO compounds to SiO2 based glasses. GEANT4 and FLUKA Monte Carlo simulation codes have been used in the planning of the samples. The glasses were produced using a well-known melt-quenching technique. The effective neutron removal cross-sections, mean free paths, half-value layer, and transmission numbers of the fabricated glasses have been calculated through both GEANT4 and FLUKA Monte Carlo simulation codes. Experimental neutron absorbed dose measurements have been carried out. It was found that GS4 glass has the best neutron protection capacity among the produced glasses. In addition to neutron shielding properties, the gamma-ray attenuation capacities, were calculated using newly developed Phy-X/PSD software. The gamma-ray shielding properties of GS1 and GS2 are found to be equivalent to Pb-based glass.eninfo:eu-repo/semantics/closedAccessGEANT4glassesMonte Carloneutron and gammashieldingArticle109214315110.1515/ract-2020-00672-s2.0-85100477638Q3WOS:000626604200007Q2