Experimental and Monte Carlo simulation study on potential new composite materials to moderate neutron-gamma radiation. (December 2020)

• Record Type: Journal Article
• Authors: Aygün, Bünyamin; Şakar, Erdem; Singh, V.P.; Sayyed, M.I.; Korkut, Turgay; Karabulut, Abdulhalik
• Is Part Of: Progress in nuclear energy. Volume 130(2020)
• Publication Date: 2020-12
• Subjects: Neutron and gamma radiation -- Epoxy -- GEANT4 -- FLUKA -- Phy-X/PSD -- Shielding metal oxide; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 333.7924
• DOI: 10.1016/j.pnucene.2020.103538
• Languages: English
• ISSNs: 0149-1970

Abstract

Abstract: In this study, 12 different concentrations of shielding materials were developed and produced. They were covered with high temperature resistant (1500 °C) sodium silicate sealing paste. Epoxy resin was produced by adding different percentages of additive materials such as chromium oxide (Cr2 O3 ), lithium (LiF), and nickel oxide (NiO). The GEANT4 and FLUKA codes of the Monte Carlo simulation toolkit were used to determine the mixing ratios. The total macroscopic cross-sections, effective removal cross-sections, mean free path, half value layer, and transmission neutron number were determined for fast neutron radiation using GEANT4 and FLUKA simulation codes. The mass attenuation coefficient, the effective atomic number and half-value layer (HVL) of the samples were calculated using Phy-X/PSD software. The absorbed dose was measured. In this study, an 241 Am–Be neutron source with 74 GBq activity and average neutron energy of approximately 4.5 MeV and a BF3 gas detector were used. Both simulation and experimental measurements were compared with paraffin and conventional concrete. The new composite shielding material absorbed radiation much better than the reference materials. This new radiation shielding composite material can be used in nuclear medicine, transport and storage of radioactive waste, nuclear power plants, and as a shielding material for neutron and gamma radiation. Highlights: 12 different type of new shielding material have been developed and produced. Gamma-ray and fast neutron shielding parameters were calculated. Experimentally equivalent dose measurements have been carried out. All new type samples have both gamma and fast neutron radiation absorption ability.