A semi–empirical method for efficiency calibration of an HPGe detector against different sample densities

Nabil, Islam M.; El-Kourghly, K.M.; Sayed, A.

doi:10.1016/j.apradiso.2023.110946

Cited by 12 publications

(2 citation statements)

References 23 publications

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“…3 . The HPGe detector was calibrated using certified γ-point sources of the radionuclides: Am-241, Cs-137, and Co-60 of 0.9 µci which also used in the investigation of the gamma rays’ attenuation 28 – 30 . The γ-point sources were measured on the front face of the ORTEC HPGe detector for 3600 s. The experimental setup is optimized, with less than 1.5% dead time and < ± 0.5% peak count rate uncertainty 31 , 32 .…”

Section: Methodsmentioning

confidence: 99%

A comprehensive study of the shielding ability from ionizing radiation of different mortars using iron filings and bismuth oxide

Al-Saleh,

Elsafi,

Almutairi

et al. 2024

Sci Rep

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The current work discusses the radiation attenuation capability and different shielding characteristics of different mortar samples. The samples were prepared by replacing different percentages of fine aggregate with iron filling and replacing different percentages of hydrated lime with Bi2O3 (0–50 wt.%). The prepared mortar samples are coded as CHBFX where X = 0, 10, 30, and 50 wt.%. The mass and linear attenuation coefficient was determined experimentally using a narrow beam technique, where a high purity germanium detector, and different point gamma-ray sources (such as Am-241, Cs-137, and Co-60). The linear attenuation coefficient was also calculated using the Monte-Carlo simulation code and the online Phy-X/PSD software. The comparison of the three methods showed a good agreement in the results. The linear attenuation coefficient drops from 19.821 to 0.053 cm−1 for CHBF0, from 27.496 to 0.057 cm−1 for CHBF10, from 42.351 to 0.064 cm−1 for CHBF30, and from 55.068 to 0.071 cm−1 for CHBF50 at photon energy range from 0.015 to 15 MeV. The half-value layer thickness, tenth-value layer thickness, and mean free path of the prepared mortar composites were also calculated photon energy ranged from 0.015 to 15 MeV. The fast neutron removal cross-section of the prepared CHBFX mortar samples have values of 0.096 cm−1, 0.098 cm−1, 0.103 cm−1, and 0.107 cm−1 for the mortar samples CHBF0, CHBF10, CHBF30, and CHBF50, respectively. The results showed that the mortar sample with the highest iron filing concentration, CHBF50, provides the best protection against gamma rays and fast neutrons which could be used in the nuclear and medical fields.

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Section: Methodsmentioning

confidence: 99%

A comprehensive study of the shielding ability from ionizing radiation of different mortars using iron filings and bismuth oxide

Al-Saleh,

Elsafi,

Almutairi

et al. 2024

Sci Rep

Self Cite

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“…The protection of workers and public against the hazards of radiation by using low-cost materials and especially waste materials is a crucial target for researchers 12 – 17 .…”

Section: Introductionmentioning

confidence: 99%

Polyurethane reinforced with micro/nano waste slag as a shielding panel for photons (experimental and theoretical study)

El-Khatib,

Abbas,

Mahmoud

et al. 2024

Sci Rep

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This study not only provides an innovative technique for producing rigid polyurethane foam (RPUF) composites, but it also offers a way to reuse metallurgical solid waste. Rigid polyurethane (RPUF) composite samples have been prepared with different proportions of iron slag as additives, with a range of 0–25% mass by weight. The process of grinding iron slag microparticles into iron slag nanoparticles powder was accomplished with the use of a high-energy ball mill. The synthesized samples have been characterized using Fourier Transform Infrared Spectroscopy, and Scanning Electron Microscope. Then, their radiation shielding properties were measured by using A hyper-pure germanium detector using point sources 241Am, 133 BA, 152 EU, 137Cs, and 60Co, with an energy range of 0.059–1.408 MeV. Then using Fluka simulation code to validate the results in the energy range of photon energies of 0.0001–100 MeV. The linear attenuation coefficient, mass attenuation coefficient, mean free path, half-value layer and tenth-value layer, were calculated to determine the radiation shielding characteristics of the composite samples. The calculated values are in good agreement with the calculated values. The results of this study showed that the gamma-ray and neutron attenuation parameters of the studied polyurethane composite samples have improved. Moreover, the effect of iron slag not only increases the gamma-ray attenuation shielding properties but also enhances compressive strength and the thermal stability. Which encourages us to use polyurethane iron-slag composite foam in sandwich panel manufacturing as walls to provide protection from radiation and also heat insulation.

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Lithium magnesium borosilicate glass: the impact of alternate doping with nano copper oxide and nano hematite on its structural, optical, and nuclear radiation shielding characteristics

Nabil,

Mosleh,

Allam

et al. 2024

J Mater Sci: Mater Electron

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A semi–empirical method for efficiency calibration of an HPGe detector against different sample densities

Cited by 12 publications

References 23 publications

A comprehensive study of the shielding ability from ionizing radiation of different mortars using iron filings and bismuth oxide

A comprehensive study of the shielding ability from ionizing radiation of different mortars using iron filings and bismuth oxide

Polyurethane reinforced with micro/nano waste slag as a shielding panel for photons (experimental and theoretical study)

Lithium magnesium borosilicate glass: the impact of alternate doping with nano copper oxide and nano hematite on its structural, optical, and nuclear radiation shielding characteristics

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