Development and production of metal oxide doped glasses for gamma ray and fast neutron shielding

• Published in: Radiation physics and chemistry (Oxford, England : 1993) England : 1993), 2020-09, Vol.174, p.108897, Article 108897
• Main Authors: Aygün, Bünyamin, Şakar, Erdem, Cinan, Esra, Yorgun, Nergiz Yıldız, Sayyed, M.I., Agar, O., Karabulut, Abdulhalik
• Format: Article
• Language: English
• Subjects: Attenuation; Bismuth oxides; Bismuth trioxide; Boron oxides; Borosilicate glass; Chromium oxides; Cobalt oxides; Concrete construction; Dosage; Fast neutrons; Gamma rays; GEANT4; Glasses; Lead oxides; Metal oxides; Monte Carlo; Neutron and gamma radiation; Neutrons; Nuclear power plants; Paraffins; Radiation shielding; Radioactive wastes; Shielding; Silicon dioxide; Silicon oxides; Tungsten
• ISSN: 0969-806X; 1879-0895
• DOI: 10.1016/j.radphyschem.2020.108897

In this study, new glasses were designed and produced that did not consist of toxic lead oxide (PbO). Unlike conventional glass with powdered silicon oxide (SiO2) added [cobalt oxide (CoO), cadmium tungsten oxide (CdWO4), bismuth oxide (Bi2O3), chromium oxide (Cr2O3), and boron oxide (B2O3)], new glass specimens were fabricated via melt-quenching. The total macroscopic cross-sections, mean free path, and transmission number were calculated using GEANT4 Monte Carlo code. The equivalent dose rates were measured for 4.5 MeV fast neutrons. Gamma attenuation experiments were conducted at several energies in a range of 53–383 keV. The experimental and theoretical results were compared with those of construction concrete, paraffin, glasses containing lead, borosilicate, normal window, and soda glasses. The new glass minimized both gamma and neutron radiation leaks that may occur in various fields such as radiation treatment, nuclear power plants, radioactive waste transport and storage, and space and laboratory research. •New glass materials have been designed and produced.•Investigate the shielding properties of gamma rays and fast neutron particles.•The Total macroscopic cross sections (cm−1), transmission number have calculated.•Fast neutron equivalent dose rate measurements were made.•Gamma attenuation experiments were performed in the range of 53–383 keV.