Numerical estimation of radiation induced volumetric expansion of igneous rocks

Khmurovska, Yuliia; Štemberk, Petr

doi:10.1063/5.0041797

Cited by 4 publications

(1 citation statement)

References 16 publications

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“…Previous studies have been conducted to investigate the damage in icted on quartz by various forms of radiation, including neutrons and other ions 117,119,120 . Khmurovska et al 121 concluded that aggregates commonly used in ordinary concrete are not suitable for application in irradiated concrete because of their high potential for RIVE. The volumetric expansion of hydrated cement paste induced by irradiation and its impact on the microstructure of aggregates has been extensively discussed in a study by Pape 122 .…”

Section: Crystallite Sizementioning

confidence: 99%

Enhancing Shielding Efficiency of Ordinary and Barite Concrete in Radiation Shielding Utilizations

Ahmad,

Idris,

Hussin

et al. 2024

Preprint

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Concrete has been used as a radiation shielding material due to its properties and integrity. Radiation shielding materials play a crucial role in various applications, ranging from nuclear power plants to medical facilities. Despite the prevalent use of concrete as a radiation-shielding material, uncertainties persist regarding the most suitable concrete grades for optimal attenuation, emphasizing the necessity for systematic investigation. In this study, we investigate the efficacy of ordinary and barite concrete as radiation shielding materials across different grades: M15, M25, M35, and M45. Ordinary concrete (OC), composed of cement, water, and limestone as aggregates, is compared with barite concrete (BC), where barite is added as an aggregate substitute to enhance radiation attenuation properties. An assessment is conducted on the physical attributes and gamma-ray attenuation characteristics of these concrete mixtures after exposure to Cobalt-60 and Caesium-137 radioactive elements. Key properties, including density, compressive strength, linear attenuation coefficient (µ), mass attenuation coefficient (µm), half-value layer (HVL), tenth-value layer (TVL), radiation protection efficiency (RPE), mean free path (MFP), radiation efficiency, and lead equivalent, were examined. The concrete is irradiated in a thermal column for 24, 48, and 72 hours to assess changes in crystalline size and lattice parameters following neutron exposure. The addition of barite as an aggregate substitute enhances the density, with the density of OC ranging from 2.1 g/cm3 to 2.39 g/cm3, accompanied by compression strength ranging from 20 MPa to 44 MPa. In contrast, barite concrete (BC) has a density ranging from 3.07 g/cm3 to 3.55 g/cm3, with compression strength ranging from 18.15 MPa to 39.71 MPa. Irradiation with Cobalt-60 reveals lower linear attenuation (µ) within the range of 0.172 to 0.195 cm− 1, with consistent mass attenuation for all grades at 0.81 cm2/g. The HVL ranges from 3.559 cm to 4.020 cm, with a corresponding TVL spanning 11.825 cm to 13.354 cm. XRD testing reveals a shift in the SiO2 and BaSO4 peaks towards the right after irradiation, indicating crystalline expansion in size, with the most significant changes observed after 24 hours of irradiation. Concerning lattice parameters, the d-value (inter-atomic spacing) shows the most significant decrease of 0.10 after 48 hours of irradiation in grade 25, while the most notable increase is 0.02 after 24 hours of irradiation in grades 15 and 45. The experiment suggests that ordinary concrete is effective for radiation shielding against 137Cs but lacks sufficient efficacy against 137Co.

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Section: Crystallite Sizementioning

confidence: 99%

Enhancing Shielding Efficiency of Ordinary and Barite Concrete in Radiation Shielding Utilizations

Ahmad,

Idris,

Hussin

et al. 2024

Preprint

View full text Add to dashboard Cite

show abstract

Enhancing shielding efficiency of ordinary and barite concrete in radiation shielding utilizations

Ahmad,

Idris,

Hussin

et al. 2024

Sci Rep

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Concrete has been widely utilized as a radiation shielding material due to its properties and structural integrity. This study aims to evaluate the efficiency of ordinary concrete versus barite concrete as radiation shielding materials, focusing on the physical aspects and changes in crystal size lattice parameters after neutron irradiation. Specifically, the research investigates the shielding effectiveness of these materials across different grades (M15, M25, M35, and M45) against gamma-ray sources Cobalt-60 and Caesium-137. The methodology involves measuring the linear attenuation coefficient (μ), half value layer (HVL), tenth value layer (TVL), and mean free path (MFP). Additionally, X-ray diffraction (XRD) was employed to assess crystallite size and lattice parameter changes post-irradiation for neutron irradiation. Results indicate that incorporating barite as an aggregate significantly enhances the density and crystallite macroscopic properties of the concrete. Irradiation with Cobalt-60 and Cesium 137 revealed that ordinary concrete has a lower linear attenuation (μ) ranging from 0.172 to 0.195 cm −1 , with consistent mass attenuation across all grades at 0.81 cm 2 /g. XRD analysis demonstrated a rightward shift in the SiO₂ and BaSO₄ peaks post-irradiation, signifying crystalline expansion. In terms of lattice parameters, the d-value showed a notable decrease of 0.10 after 48 h of irradiation in grade 25, while the most significant increase of 0.02 occurred after 24 h of irradiation in grades 15 and 45. In conclusion, barite concrete proves to be more effective for radiation shielding in nuclear facilities, whereas ordinary concrete is suitable for medical shielding, or facilities exposed to lower radiation doses.

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