A unique Vietnam's red clay-based brick reinforced with metallic wastes for γ-ray shielding purposes: Fabrication, characterization, and γ-ray attenuation properties
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A unique brick series based on Vietnamese clay was manufactured at 114.22 MPa pressure rate for γ-ray attenuation purposes, consisting of (x) metallic waste & (90%-x) red clay mineral & 10% (hardener mixed with epoxy resin), where (x) is equal to the values 0%, 20%, 40%, 50%, and 70%. The impacts of industrial metal waste ratio in the structure and radiation protective characteristics were evaluated experimentally. The increase in metallic waste doping concentrations from 0% to 70% was associated with an increase in the manufactured brick’s density (ρ) from 2.103 to 2.256 g/cm3 while the fabricated samples’ porosity (Φ) decreased from 11.7 to 1.0%, respectively. Together with a rise in fabricated brick’s density and a decrease in their porosities, the manufactured bricks’ γ-ray attenuation capacities improved. The measured linear attenuation coefficient (μ, cm 1) was improved by 30.8%, 22.1%, 21.6%, and 19.7%, at Eγ equal to the values respectively 0.662, 1.173, 1.252, and 1.332 MeV, when the metallic waste concentration increased from 0% to 70%, respectively. The study demonstrates that manufactured bricks exhibit superior radiation shielding properties, with radiation protection efficiencies of 88.4%, 90.0%, 91.7%, 92.1%, and 92.4% for bricks with industrial metal waste contents of 0%, 20%, 40%, 50%, and 70%, respectively, at γ-ray energy (Eγ) of 1.332 MeV
Abstract
A unique brick series based on Vietnamese clay was manufactured at 114.22 MPa pressure rate for γ-ray attenuation purposes, consisting of (x) metallic waste & (90%-x) red clay mineral & 10% (hardener mixed with epoxy resin), where (x) is equal to the values 0%, 20%, 40%, 50%, and 70%. The impacts of industrial metal waste ratio in the structure and radiation protective characteristics were evaluated experimentally. The increase in metallic waste doping concentrations from 0% to 70% was associated with an increase in the manufactured brick’s density (ρ) from 2.103 to 2.256 g/cm3 while the fabricated samples’ porosity (Φ) decreased from 11.7 to 1.0%, respectively. Together with a rise in fabricated brick’s density and a decrease in their porosities, the manufactured bricks’ γ-ray attenuation capacities improved. The measured linear attenuation coefficient (μ, cm 1) was improved by 30.8%, 22.1%, 21.6%, and 19.7%, at Eγ equal to the values respectively 0.662, 1.173, 1.252, and 1.332 MeV, when the metallic waste concentration increased from 0% to 70%, respectively. The study demonstrates that manufactured bricks exhibit superior radiation shielding properties, with radiation protection efficiencies of 88.4%, 90.0%, 91.7%, 92.1%, and 92.4% for bricks with industrial metal waste contents of 0%, 20%, 40%, 50%, and 70%, respectively, at γ-ray energy (Eγ) of 1.332 MeV
참고문헌 (37)
- W. Du, "Nuclear targeting Subcellular-delivery nanosystems for precise cancer treatment", Int. J. Pharm, 619, pp.121735~ (2022)[DOI]
- S. Tanaka, "Improvement of resistance to oxaliplatin by vorinostat in human colorectal cancer cells through inhibition of Nrf2 nuclear translocation", Biochem. Biophys. Res. Commun, 607, pp.9~14 (2022)[DOI]
- H. M. O. Parker, "The use of ionising radiation to image nuclear fuel : a review", Prog. Nucl. Energy, 85, pp.297~318 (2015)[DOI]
- M. F. Marcone, "Diverse foodbased applications of nuclear magnetic resonance(NMR)technology", Food Res. Int, 51, pp.729~747 (2013)[DOI]
- O. Desouky, "Targeted and non-targeted effects of ionizing radiation", J Radiat Res Appl Sci, 8, pp.247~254 (2015)[DOI]
- M. Sadiq, "Environmental footprint impacts of nuclear energy consumption : the role of environmental technology and globalization in ten largest ecological footprint countries", Nucl. Eng. Technol, 54, pp.3672~3681 (2022)[DOI]
- O. L. Tashlykov, "Reducing the exposure dose by optimizing the route of personnel movement when visiting specified points and taking into account the avoidance of obstacles", Energies, 15, pp.8222~ (2022)[DOI]
- A. F. Mikhailova, "The ways of implementation of the optimization principle in the personnel radiological protection", Phys. Atom. Nucl, 83, pp.1718~1726 (2020)[DOI]
- ICRP, "The 2007 recommendations of the international commission on radiological protection", Ann. ICRP, 37(2–4) (2007), ICRP publication
- IAEA, "Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, 2014. No. GSR Part 3", ~ (2014)
- O. L. Tashlykov, "Development of methods for route optimization of work in inhomogeneous radiation fields to minimize the dose load of personnel", Energies, 15, pp.4788~ (2022)[DOI]
- Y. A. Kropachev, "Optimization of radiation protection at the NPP unit decommissioning stage, Izvestiya Wysshikh Uchebnykh Zawedeniy", Yadernaya Energetika, 2019, pp.119~130 (2019)[DOI]
- Yu V. Nosov, "Decommissioning features of BN-350, -600 fast reactors", Atom. Energy, 125, pp.219~223 (2019)[DOI]
- O. L. Tashlykov, "The optimization of radiation protection composition, Izvestiya Wysshikh Uchebnykh Zawedeniy", Yadernaya Energetika, 2015, pp.36~42 (2015)[DOI]
- O.L. Tashlykov, "Composition optimization of homogeneous radiation-protective materials for planned irradiation conditions", Atom. Energy, 121, pp.303~307 (2017)[DOI]
- K. A. Mahmoud, "A new heavy-mineral doped clay brick for gamma-ray protection purposes", Appl. Radiat. Isot, 173, pp.109720~ (2021)[DOI]
- H. Durak, "The impact of Co addition on neutron-photon protection characteristics of red and yellow clays-based bricks : an experimental study", Prog. Nucl. Energy, 143, pp.104047~ (2022)[DOI]
- H. S. Mann, "Gamma-ray shielding effectiveness of novel light-weight clay-flyash bricks", Radiat. Phys. Chem, 127, pp.97~101 (2016)[DOI]
- S. Kiatwattanacharoen, "A Study of X-Ray Radiation Shielding Properties of Bricks Contained Barium Sulfate", pp.060004~ (2020)[DOI]
- K. A. Mahmoud, "Modeling a three-layer container based on halloysite nano-clay for radioactive waste disposal", Prog. Nucl. Energy, 152 (2022)[DOI]
- K. S. Mann, "Investigation of clay bricks for storage facilities of radioactive-wastage", Appl. Clay Sci, 119, pp.249~256 (2016)[DOI]
- B. S. Sidhu, "On the use of flyash-lime-gypsum(FaLG)bricks in the storage facilities for low level nuclear waste", Nucl. Eng. Technol, 54, pp.674~680 (2022)[DOI]
- L. A. Escalera-Velasco, "Radiation shielding and dosimetric parameters of mexican artisanal bricks", Appl. Radiat. Isot, 188, pp.110355~ (2022)[DOI]
- L. A. Escalera-Velasco, "Shielding behavior of artisanal bricks against ionizing photons", Appl. Radiat. Isot, 161, pp.109167~ (2020)[DOI]
- M. I. Sayyed, "A comprehensive study of the energy absorption and exposure buildup factors of different bricks for gamma-rays shielding", Results Phys, 7, pp.2528~2533 (2017)[DOI]
- B. Albarzan, "Effect of Fe2O3 doping on structural, FTIR and radiation shielding characteristics of aluminium-lead-borate glasses", Prog. Nucl. Energy, 141, pp.103931~ (2021)[DOI]
- M. I. Sayyed, "Theoretical Investigation of the radiation-protection properties of the CBS glass family", Optik, 258, pp.168851~ (2022)[DOI]
- K. G. Mahmoud, "The influence of heavy metallic wastes on the physical properties and gamma-ray shielding performance of ordinary concrete : experimental evaluations", Radiat. Phys. Chem, 206, pp.110793~ (2023)[DOI]
- R. S. Aita, "Impacts of siltstone rocks on the ordinary concrete’s physical, mechanical and gamma-ray shielding properties: an experimental examination", Nucl. Eng. Technol (2024)[DOI]
- I. Akkurt, "Radiation transmission of concrete including pumice for 662, 1173 and 1332keV gamma rays", Nucl. Eng. Des, 252, pp.163~166 (2012)[DOI]
- I. Akkurt, "Study on dependence of partial and total mass attenuation coefficients", J. Quant. Spectrosc. Radiat. Transf, 94, pp.379~385 (2005)[DOI]
- I. Akkurt, "The photon attenuation coefficients of barite, marble and limra", Ann. Nucl. Energy, 31, pp.577~582 (2004)[DOI]
- E. O. Echeweozo, "Investigation of kaolin-granite composite bricks for gamma radiation shielding", International Journal of Advanced Nuclear Reactor Design and Technology, 3, pp.194~199 (2021)[DOI]
- H. S. Mann, "Experimental investigation of clay fly ash bricks for gamma-ray shielding", Nucl. Eng. Technol, 48, pp.1230~1236 (2016)[DOI]
- B. Dogan, "Investigation of Photon Attenuation Coefficient of Some Building Materials Used in Turkey", pp.020033~ (2015)[DOI]
- H. S. Isfahani, "Investigation on gamma-ray shielding and permeability of clay-steel slag mixture", Bull. Eng. Geol. Environ, 78, pp.4589~4598 (2019)[DOI]
- H. Share Isfahani, "Permeability and gamma-ray shielding efficiency of clay modified by barite powder", Geotech. Geol. Eng, 37, pp.845~855 (2019)[DOI]