New high temperature resistant heavy concretes for fast neutron and gamma radiation shielding
-
Bünyamin Aygün
,
Erdem Şakar
Abstract
In the present work, we developed three new high temperature resistant heavy concretes as novel radiation shielding materials. For this purpose, chrome ore (FeCr2O4), hematite (Fe2O3), titanium oxide (TiO2), aluminum oxide (Al2O3), limonite [FeO (OH) nH2O], siderite (FeCO3), barite (BaSO4), nickel oxide (NiO) materials and alumina cement were used. Mass combination ratios of components and total macroscopic cross sections (scattering, absorption, capture, fission) of the samples were calculated by using GEANT4 code. The resistances of the prepared samples were evaluated in terms of compression strength after exposure at the 1000 °C temperature. Neutron equivalent dose rate measurements were carried out by using 4.5 MeV 241Am-Be neutron source and BF3 detector. All results were compared with normal weight concrete and paraffin. The results of neutron dose indicate that neutron absorption ability of the new heavy concretes is higher than normal weight concrete and paraffin. In addition to neutron measurements, different γ-ray shielding parameters such as mass attenuation coefficient (MAC), effective atom numbers (Zeff), half value layer (HVL) and mean free path (MFP) have been calculated using WinXCOM software in order to investigate the effectiveness of using the prepared concretes as a radiation shielding materials. Gamma-ray results were compared with concretes and Pb-based glass.
Funding source: Ataturk University
Award Identifier / Grant number: 2016/FM71
Funding source: Agri Ibrahim Cecen University
Award Identifier / Grant number: MYO.18.001
Funding statement: This work is financially supported by Ataturk University with Grant No. 2016/FM71 and Agri Ibrahim Cecen University with Grant no. MYO.18.001.
Compliance with Ethical Standards: The authors declare that they have no conflict of interest.
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©2019 Walter de Gruyter GmbH, Berlin/Boston
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Articles in the same Issue
- Frontmatter
- Cross-section measurements and production of 72Se with medium to high energy protons using arsenic containing targets
- Thorium oxide dissolution in HNO3-HF mixture: kinetics and mechanism
- Highly efficient carbonaceous nanofiber/layered double hydroxide nanocomposites for removal of U(VI) from aqueous solutions
- Effect of solution acidity on the structure of amino acid-bearing uranyl compounds
- A novel method for the determination of uranium and free acidity in nuclear fuel process samples by extraction spectrophotometry
- Experimental investigation of photon attenuation parameters for different binary alloys
- Radiation protective characteristics of some selected tungstates
- New high temperature resistant heavy concretes for fast neutron and gamma radiation shielding
