Experimental and Monte Carlo simulation study on potential new composite materials to moderate neutron-gamma radiation

被引：31
作者：
Aygun, Bunyamin [1 ]
Sakar, Erdem [2 ]
Singh, V. P. [3 ]
Sayyed, M. I. [4 ,5 ]
Korkut, Turgay [6 ]
Karabulut, Abdulhalik [7 ]
机构：
[1] Ibrahim Cecen Univ Agri, Vocat Sch, Dept Elect & Automat, Agri, Turkey
[2] Ataturk Univ, Fac Sci, Dept Phys, TR-25240 Erzurum, Turkey
[3] Karnatak Univ, Dept Phys, Dharwad, Karnataka, India
[4] Isra Univ, Fac Sci, Dept Phys, Amman, Jordan
[5] Imam Abdulrahman Bin Faisal Univ, Inst Res & Med Consultat, Dept Nucl Med Res, Dammam, Saudi Arabia
[6] Sinop Univ, Fac Engn, Dept Nucl Engn, Sinop, Turkey
[7] Ibrahim Cecen Univ Agri, Ataturk Univ, Fac Sci, Dept Phys, TR-25240 Agri, Turkey
来源：
PROGRESS IN NUCLEAR ENERGY | 2020年 / 130卷
关键词：
Neutron and gamma radiation; Epoxy; GEANT4; FLUKA; Phy-X/PSD; Shielding metal oxide;
D O I：
10.1016/j.pnucene.2020.103538
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
In this study, 12 different concentrations of shielding materials were developed and produced. They were covered with high temperature resistant (1500 degrees C) sodium silicate sealing paste. Epoxy resin was produced by adding different percentages of additive materials such as chromium oxide (Cr2O3), 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 Am-241-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.
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页数：9
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