Bentonite based ceramic materials from a perspective of gamma-ray shielding: Preparation, characterization and performance evaluation

Sinan Asal; Sema Akyil Erenturk; Sevilay Haciyakupoglu

doi:10.1016/j.net.2020.11.009

Bentonite based ceramic materials from a perspective of gamma-ray shielding: Preparation, characterization and performance evaluation

Sinan Asal, Sema Akyil Erenturk^*, Sevilay Haciyakupoglu

^*Corresponding author for this work

Energy Institute

Istanbul Technical University

Research output: Contribution to journal › Article › peer-review

25 Citations (Scopus)

Abstract

Exposure to gamma-rays is hazardous for humans and other living beings because of their high penetration through the materials. For this reason, shielding materials (usually lead, copper and stainless steel) are used to protect against gamma rays. This study's objective was to prepare ceramic materials for gamma radiation shielding by using different natural bentonite clays. Gamma-ray attenuation performances of the prepared shielding materials at different thicknesses were investigated and evaluated for different gamma-ray energies from different standard point gamma radiation sources (²⁵¹Am, ⁵⁷Co, ¹³⁷Cs, ⁶⁰Co, and ⁸⁸Y). The mass and linear attenuation coefficients of the prepared ceramics vary between 0.238 and 0.443 cm² g⁻¹ and between 0.479 and 1.06 cm⁻¹, respectively, depending on their thicknesses. Results showed that these materials could be prioritized because of their evidential properties of gamma radiation protection in radiation applications.

Original language	English
Pages (from-to)	1634-1641
Number of pages	8
Journal	Nuclear Engineering and Technology
Volume	53
Issue number	5
DOIs	https://doi.org/10.1016/j.net.2020.11.009
Publication status	Published - May 2021

Bibliographical note

Publisher Copyright:
© 2020 Korean Nuclear Society

Funding

This work is part of the project supported by the Istanbul Technical University Research Foundation (Project No: 39416). We gratefully acknowledge Czech Metrology Institute-Inspectorate for Ionizing Radiation for providing the standard gamma-ray point sources. This work is part of the project supported by the Istanbul Technical University Research Foundation (Project No: 39416 ). We gratefully acknowledge Czech Metrology Institute-Inspectorate for Ionizing Radiation for providing the standard gamma-ray point sources.

Funders	Funder number
Czech Metrology Institute-Inspectorate
Istanbul Technical University Research Foundation	39416

Keywords

Attenuation coefficient
Bentonite
Ceramic
Gamma-ray shielding
Half value thickness
Tenth value thickness

Access to Document

10.1016/j.net.2020.11.009

Cite this

@article{6711137204c64fdaa26d2f9ecd909f5d,

title = "Bentonite based ceramic materials from a perspective of gamma-ray shielding: Preparation, characterization and performance evaluation",

abstract = "Exposure to gamma-rays is hazardous for humans and other living beings because of their high penetration through the materials. For this reason, shielding materials (usually lead, copper and stainless steel) are used to protect against gamma rays. This study's objective was to prepare ceramic materials for gamma radiation shielding by using different natural bentonite clays. Gamma-ray attenuation performances of the prepared shielding materials at different thicknesses were investigated and evaluated for different gamma-ray energies from different standard point gamma radiation sources (251Am, 57Co, 137Cs, 60Co, and 88Y). The mass and linear attenuation coefficients of the prepared ceramics vary between 0.238 and 0.443 cm2 g−1 and between 0.479 and 1.06 cm−1, respectively, depending on their thicknesses. Results showed that these materials could be prioritized because of their evidential properties of gamma radiation protection in radiation applications.",

keywords = "Attenuation coefficient, Bentonite, Ceramic, Gamma-ray shielding, Half value thickness, Tenth value thickness",

author = "Sinan Asal and Erenturk, {Sema Akyil} and Sevilay Haciyakupoglu",

note = "Publisher Copyright: {\textcopyright} 2020 Korean Nuclear Society",

year = "2021",

month = may,

doi = "10.1016/j.net.2020.11.009",

language = "English",

volume = "53",

pages = "1634--1641",

journal = "Nuclear Engineering and Technology",

issn = "1738-5733",

publisher = "Korean Nuclear Society",

number = "5",

}

TY - JOUR

T1 - Bentonite based ceramic materials from a perspective of gamma-ray shielding

T2 - Preparation, characterization and performance evaluation

AU - Asal, Sinan

AU - Erenturk, Sema Akyil

AU - Haciyakupoglu, Sevilay

PY - 2021/5

Y1 - 2021/5

N2 - Exposure to gamma-rays is hazardous for humans and other living beings because of their high penetration through the materials. For this reason, shielding materials (usually lead, copper and stainless steel) are used to protect against gamma rays. This study's objective was to prepare ceramic materials for gamma radiation shielding by using different natural bentonite clays. Gamma-ray attenuation performances of the prepared shielding materials at different thicknesses were investigated and evaluated for different gamma-ray energies from different standard point gamma radiation sources (251Am, 57Co, 137Cs, 60Co, and 88Y). The mass and linear attenuation coefficients of the prepared ceramics vary between 0.238 and 0.443 cm2 g−1 and between 0.479 and 1.06 cm−1, respectively, depending on their thicknesses. Results showed that these materials could be prioritized because of their evidential properties of gamma radiation protection in radiation applications.

AB - Exposure to gamma-rays is hazardous for humans and other living beings because of their high penetration through the materials. For this reason, shielding materials (usually lead, copper and stainless steel) are used to protect against gamma rays. This study's objective was to prepare ceramic materials for gamma radiation shielding by using different natural bentonite clays. Gamma-ray attenuation performances of the prepared shielding materials at different thicknesses were investigated and evaluated for different gamma-ray energies from different standard point gamma radiation sources (251Am, 57Co, 137Cs, 60Co, and 88Y). The mass and linear attenuation coefficients of the prepared ceramics vary between 0.238 and 0.443 cm2 g−1 and between 0.479 and 1.06 cm−1, respectively, depending on their thicknesses. Results showed that these materials could be prioritized because of their evidential properties of gamma radiation protection in radiation applications.

KW - Attenuation coefficient

KW - Bentonite

KW - Ceramic

KW - Gamma-ray shielding

KW - Half value thickness

KW - Tenth value thickness

UR - http://www.scopus.com/inward/record.url?scp=85097046030&partnerID=8YFLogxK

U2 - 10.1016/j.net.2020.11.009

DO - 10.1016/j.net.2020.11.009

M3 - Article

AN - SCOPUS:85097046030

SN - 1738-5733

VL - 53

SP - 1634

EP - 1641

JO - Nuclear Engineering and Technology

JF - Nuclear Engineering and Technology

IS - 5

ER -

Bentonite based ceramic materials from a perspective of gamma-ray shielding: Preparation, characterization and performance evaluation

Abstract

Bibliographical note

Funding

Keywords

Access to Document

Other files and links

Fingerprint

Cite this