Experimental and Monte Carlo simulation study on potential new composite materials to moderate neutron-gamma radiation
Yazarlar (4)
Bünyamin Aygün Ağrı İbrahim Çeçen Üniversitesi, Türkiye
Doç. Dr. Erdem Şakar Atatürk Üniversitesi, Türkiye
Prof. Dr. Abdulhalik KARABULUT Atatürk Üniversitesi, Türkiye
Prof. Dr. Turgay KORKUT Sinop Üniversitesi, Türkiye
| Makale Türü | Özgün Makale (SSCI, AHCI, SCI, SCI-Exp dergilerinde yayınlanan tam makale) | ||
| Dergi Adı | PROGRESS IN NUCLEAR ENERGY (Q1) | ||
| Dergi ISSN | 0149-1970 Dergi Bilgileri (2020) | ||
| Dergi Tarandığı Indeksler | SCI-Expanded | ||
| Makale Dili | Türkçe | Basım Tarihi | 12-2020 |
| Cilt / Sayı / Sayfa | 130 / 0 / 103538–0 | DOI | 10.1016/j.pnucene.2020.103538 |
| UAK Araştırma Alanları |
Radyasyon Teknolojisi
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| Özet |
| 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 (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 241Am–Be neutron source with 74 GBq activity … |
| Anahtar Kelimeler |
| Neutron and gamma radiation | Epoxy | GEANT4 | FLUKA | Phy-X/PSD | Shielding metal oxide |
BM Sürdürülebilir Kalkınma Amaçları
| Atıf Sayıları | |
| Web of Science | 37 |
| Google Scholar | 44 |