Standard

Impacts of sintering temperature on the mechanical properties and gamma ray protection capacity of clay bricks. / Almuqrin, Aljawhara; Mahmoud, K.; Sayyed, M. и др.
в: Nuclear Engineering and Technology, Том 56, № 7, 01.07.2024, стр. 2489-2497.

Результаты исследований: Вклад в журналСтатьяРецензирование

Harvard

Almuqrin, A, Mahmoud, K, Sayyed, M & Al-Ghamdi, H 2024, 'Impacts of sintering temperature on the mechanical properties and gamma ray protection capacity of clay bricks', Nuclear Engineering and Technology, Том. 56, № 7, стр. 2489-2497. https://doi.org/10.1016/j.net.2024.02.007

APA

Vancouver

Almuqrin A, Mahmoud K, Sayyed M, Al-Ghamdi H. Impacts of sintering temperature on the mechanical properties and gamma ray protection capacity of clay bricks. Nuclear Engineering and Technology. 2024 июль 1;56(7):2489-2497. doi: 10.1016/j.net.2024.02.007

Author

Almuqrin, Aljawhara ; Mahmoud, K. ; Sayyed, M. и др. / Impacts of sintering temperature on the mechanical properties and gamma ray protection capacity of clay bricks. в: Nuclear Engineering and Technology. 2024 ; Том 56, № 7. стр. 2489-2497.

BibTeX

@article{e2288a943c334f5b82c0c210a2049c03,
title = "Impacts of sintering temperature on the mechanical properties and gamma ray protection capacity of clay bricks",
abstract = "The current study aims to develop new clay bricks doped with metallic waste for radiation shielding applications. The aforementioned new bricks were fabricated with various metallic waste concentrations under a pressure rate reaching ≈114 MPa and firing temperature of 1100 °C. The impacts of the metallic waste and the firing temperature on the developed brick samples' physical, radiation shielding, and structural properties were studied. In order to identify the fabricated bricks' mineral content, the X-ray diffraction pattern was used. Additionally, the fabricated bricks' porosity and density were experimentally determined, where the porosity was reduced by 28.03%, while their densities increased by ≈ 10.5% by raising the concentration of metallic waste. The linear attenuation coefficient (LAC) for the developed brick was investigated experimentally using a NaI (Tl) scintillation detector over the 0.033–1.408 MeV energy interval. The measured LAC values were enhanced by increasing the concentrations of metallic waste within the fabricated bricks over the examined energy interval. The fabricated brick's LAC enhancement improves the gamma-ray shielding characteristics. Therefore, the fabricated bricks are a cheap and suitable choice for radiation protection applications.",
author = "Aljawhara Almuqrin and K. Mahmoud and M. Sayyed and H. Al-Ghamdi",
note = "The authors extend their appreciation to the Deputyship for Research & Innovation, Ministry of Education in Saudi Arabia for funding this research work through the project number RI-44-0352.",
year = "2024",
month = jul,
day = "1",
doi = "10.1016/j.net.2024.02.007",
language = "English",
volume = "56",
pages = "2489--2497",
journal = "Nuclear Engineering and Technology",
issn = "1738-5733",
publisher = "Elsevier",
number = "7",

}

RIS

TY - JOUR

T1 - Impacts of sintering temperature on the mechanical properties and gamma ray protection capacity of clay bricks

AU - Almuqrin, Aljawhara

AU - Mahmoud, K.

AU - Sayyed, M.

AU - Al-Ghamdi, H.

N1 - The authors extend their appreciation to the Deputyship for Research & Innovation, Ministry of Education in Saudi Arabia for funding this research work through the project number RI-44-0352.

PY - 2024/7/1

Y1 - 2024/7/1

N2 - The current study aims to develop new clay bricks doped with metallic waste for radiation shielding applications. The aforementioned new bricks were fabricated with various metallic waste concentrations under a pressure rate reaching ≈114 MPa and firing temperature of 1100 °C. The impacts of the metallic waste and the firing temperature on the developed brick samples' physical, radiation shielding, and structural properties were studied. In order to identify the fabricated bricks' mineral content, the X-ray diffraction pattern was used. Additionally, the fabricated bricks' porosity and density were experimentally determined, where the porosity was reduced by 28.03%, while their densities increased by ≈ 10.5% by raising the concentration of metallic waste. The linear attenuation coefficient (LAC) for the developed brick was investigated experimentally using a NaI (Tl) scintillation detector over the 0.033–1.408 MeV energy interval. The measured LAC values were enhanced by increasing the concentrations of metallic waste within the fabricated bricks over the examined energy interval. The fabricated brick's LAC enhancement improves the gamma-ray shielding characteristics. Therefore, the fabricated bricks are a cheap and suitable choice for radiation protection applications.

AB - The current study aims to develop new clay bricks doped with metallic waste for radiation shielding applications. The aforementioned new bricks were fabricated with various metallic waste concentrations under a pressure rate reaching ≈114 MPa and firing temperature of 1100 °C. The impacts of the metallic waste and the firing temperature on the developed brick samples' physical, radiation shielding, and structural properties were studied. In order to identify the fabricated bricks' mineral content, the X-ray diffraction pattern was used. Additionally, the fabricated bricks' porosity and density were experimentally determined, where the porosity was reduced by 28.03%, while their densities increased by ≈ 10.5% by raising the concentration of metallic waste. The linear attenuation coefficient (LAC) for the developed brick was investigated experimentally using a NaI (Tl) scintillation detector over the 0.033–1.408 MeV energy interval. The measured LAC values were enhanced by increasing the concentrations of metallic waste within the fabricated bricks over the examined energy interval. The fabricated brick's LAC enhancement improves the gamma-ray shielding characteristics. Therefore, the fabricated bricks are a cheap and suitable choice for radiation protection applications.

UR - http://www.scopus.com/inward/record.url?partnerID=8YFLogxK&scp=85184780537

U2 - 10.1016/j.net.2024.02.007

DO - 10.1016/j.net.2024.02.007

M3 - Article

VL - 56

SP - 2489

EP - 2497

JO - Nuclear Engineering and Technology

JF - Nuclear Engineering and Technology

SN - 1738-5733

IS - 7

ER -

ID: 58887362