Published September 2021 | Version v1
Journal article

Gamma and neutron attenuation characteristics of bricks containing zinc extraction residue as a novel shielding material

  • 1. Bartin University, Faculty of Engineering, Architecture and Design, Department of Civil Engineering, 74100, Bartin (Turkey)
  • 2. Akdeniz University, Faculty of Engineering, Department of Biomedical Engineering, 07058, Antalya (Turkey)
  • 3. Yildiz Technical University, Faculty of Arts & Science, Department of Physics, 34220, Istanbul (Turkey)
  • 4. Bartin University, Faculty of Engineering, Architecture and Design, Department of Metallurgical and Materials Engineering, 74110, Bartin (Turkey)
  • 5. Bartin University, Faculty of Engineering, Architecture and Design, Department of Environmental Engineering, 74110, Bartin (Turkey)
  • 6. Izmir Katip Celebi University, Faculty of Engineering and Architecture, Department of Materials Science and Engineering, 35620, Izmir (Turkey)

Description

Highlights: • Radiation shielding characteristics of brick with zinc extraction residue (ZER) was studied. • MCNP results were checked against those produced from XCOM database and Phy-X/PSD. • Addition of ZER into brick increase its shielding performance. • ZER inclusion increases bulk density of clay brick while decreasing compressive strength. • Study presents sustainable approach for conventional technology in nuclear applications. In recent years, people are exposed to radiation depending on the technology developed which may cause serious incurable health problems. To protect from radiation exposure, various radiation shielding materials are used in different areas. In this study, zinc extraction residue (ZER), which is released during zinc production containing various heavy metals, was evaluated in clay-based brick manufacturing. The fired bricks were characterized in terms of radiation shielding, bulk density and compressive strength. Clay brick with 50% ZER was fired at 1000 °C. Bulk density and compressive strength of fired brick were found as 2.16 g/cm3 and 12.6 MPa, respectively. The addition of ZER increased the density while reducing the compressive strength. Radiation shielding potential for the samples were evaluated both experimentally (using an Am–Be neutron source and a Cs-137 gamma source) and simulation-wise using the Monte Carlo technique. For this purpose, mass attenuation coefficients of gammas and total absorption cross-section of neutrons were determined through measurements. Additionally, Monte Carlo simulations were carried out under similar irradiation conditions. The MCNP simulation results were checked against those produced from XCOM database for photons and Phy-X/PSD for neutrons. Inclusion of ZER was found to elevate shielding capabilities especially at low photon energies because of the lead content of ZER. In addition, neutron attenuation characteristics of ZER bricks were observed to be relatively lower than that of fired clay brick because of the heavier ingredients existing in ZER extracts.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.pnucene.2021.103878

Additional details

Identifiers

DOI
10.1016/j.pnucene.2021.103878;
PII
S0149197021002419;

Publishing Information

Journal Title
Progress in Nuclear Energy
Journal Volume
139
Journal Page Range
vp.
ISSN
0149-1970
CODEN
PNENDE

Optional Information

Copyright
Copyright (c) 2021 Elsevier Ltd. All rights reserved.