CdO-rich quaternary tellurite glasses for nuclear safety purposes: Synthesis and experimental gamma-ray and neutron radiation assessment of high-density and transparent samples

Kılıç, Gökhan; Kavaz, Esra; İlik, Erkan; ALMisned, Ghada; Tekın, H.O.

doi:10.1016/j.optmat.2022.112512

Cited by 33 publications

(12 citation statements)

References 39 publications

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“…Finally, it should be noted that in recent years, the research and development of various combinations of glass, polymer, and nanoparticle compositions for radiation protection has become a highly topical, and as a result, many different glass combinations have been successfully synthesized and evaluated [ 41 , 42 , 43 , 44 , 45 , 46 , 47 , 48 , 49 , 50 , 51 , 52 , 53 , 54 , 55 , 56 , 57 , 58 ].…”

Section: Resultsmentioning

confidence: 99%

Investigation of the Efficiency of Shielding Gamma and Electron Radiation Using Glasses Based on TeO2-WO3-Bi2O3-MoO3-SiO to Protect Electronic Circuits from the Negative Effects of Ionizing Radiation

et al. 2022

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This article considers the effect of MoO3 and SiO additives in telluride glasses on the shielding characteristics and protection of electronic microcircuits operating under conditions of increased radiation background or cosmic radiation. MoO3 and SiO dopants were chosen because their properties, including their insulating characteristics, make it possible to avoid breakdown processes caused by radiation damage. The relevance of the study consists in the proposed method of using protective glasses to protect the most important components of electronic circuits from the negative effects of ionizing radiation, which can cause failures or lead to destabilization of the electronics. Evaluation of the shielding efficiency of gamma and electron radiation was carried out using a standard method for determining the change in the threshold voltage (∆U) value of microcircuits placed behind the shield and subjected to irradiation with various doses. It was established that an increase in the content of MoO3 and SiO in the glass structure led to an increase of up to 90% in the gamma radiation shielding efficiency, while maintaining the stability of microcircuit performance under prolonged exposure to ionizing radiation. The results obtained allow us to conclude that the use of protective glasses based on TeO2–WO3–Bi2O3–MoO3–SiO is highly promising for creating local protection for the main components of microcircuits and semiconductor devices operating under conditions of increased background radiation or cosmic radiation.

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Section: Resultsmentioning

confidence: 99%

Investigation of the Efficiency of Shielding Gamma and Electron Radiation Using Glasses Based on TeO2-WO3-Bi2O3-MoO3-SiO to Protect Electronic Circuits from the Negative Effects of Ionizing Radiation

et al. 2022

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“…Monte Carlo simulations have been used efficiently in radiation protection [ 13 , 14 , 15 , 16 ], materials research [ 17 , 18 , 19 , 20 ], detector design [ 21 , 22 , 23 ], and medical applications [ 24 ]. In this work, two different 2 × 2 inch NaI(Tl) and LaBr3(Ce) scintillation detectors were modeled in terms of their full energy peak efficiency measurements and comparisons.…”

Section: Methodsmentioning

confidence: 99%

A closer look at the efficiency calibration of LaBr3(Ce) and NaI(Tl) scintillation detectors using MCNPX for various types of nuclear investigations

ALMisned

Zakaly

Ali

et al. 2022

Heliyon

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“…In previous studies, the C40 sample, which is one of the glass samples synthesized due to the P 2 O 5 -TeO 2 -ZnO/CdO structure [16][17][18][19], was obtained by melt-quenching method. C40 sample with initial composition of 20P 2 O 5 .30TeO 2 .10ZnO.40CdO (in mol%) was melted in a platinum crucible at 900 °C using high purity chemicals and annealed at approximately 385 °C to balance the internal forces.…”

Section: C40 Glass Sample Synthesismentioning

confidence: 99%

“…Since the high density of radiation shielding materials significantly changes the properties of the relevant material, CdO is an important oxidized compound in this and similar studies. In our previous studies, P 2 O 5 -TeO 2 -ZnO glasses containing CdO in different ratios [16][17][18][19] optical, physical and radiation shielding properties are emphasized. These characterizations are handled at low ratios of CdO and high ratios of CdO.…”

Section: Introductionmentioning

confidence: 99%

“…These characterizations are handled at low ratios of CdO and high ratios of CdO. Experimental neutron shielding characterization using 133Ba radioisotope and experimental gamma-ray using a 241 Am/Be neutron source, compared to glasses with low CdO [19], samples with high CdO [18] showed better results. In fact, in these studies, it was determined that the sample containing 40 mol% CdO, coded as C40, gave the most effective result.…”

Section: Introductionmentioning

confidence: 99%

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A critical evaluation on nuclear safety properties of novel cadmium oxide-rich glass containers for transportation and waste management: Benchmarking with a reinforced concrete container

et al. 2022

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We examine the nuclear safety properties of a newly designed cadmium oxide-rich glass container for nuclear material to a bitumen-reinforced concrete container. Individual transmission factors, detector modelling, and energy deposition (MeV/g) in the air are calculated using MCNPX (version 2.7.0) general purpose Monte Carlo code. Two container configurations are designed with the material properties of cadmium dioxide-rich glass and Concrete + Bitument in consideration. First, individual transmission factors for 60Co and 137Cs radioisotopes are calculated. To evaluate potential environmental consequences, energy deposition amounts in the air for 60Co and 137Cs are also determined. The minimum gamma-ray transmission rates for two container types are reported for a cadmium dioxide-rich glass container. In addition, the quantity of energy deposition is varied depending on the container type, with a lower value for cadmium dioxide-rich glass container. The 40% cadmium dioxide-doped glass container provides more effective safety than the Cement + Bitumen container, according to the overall findings. In conclusion, the utilization of cadmium dioxide-doped glass material along with its high transparency and advanced material properties may be a significant and effective option in areas where concrete is required to assure the safety of nuclear materials.

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CdO-rich quaternary tellurite glasses for nuclear safety purposes: Synthesis and experimental gamma-ray and neutron radiation assessment of high-density and transparent samples

Cited by 33 publications

References 39 publications

Investigation of the Efficiency of Shielding Gamma and Electron Radiation Using Glasses Based on TeO2-WO3-Bi2O3-MoO3-SiO to Protect Electronic Circuits from the Negative Effects of Ionizing Radiation

Investigation of the Efficiency of Shielding Gamma and Electron Radiation Using Glasses Based on TeO2-WO3-Bi2O3-MoO3-SiO to Protect Electronic Circuits from the Negative Effects of Ionizing Radiation

A closer look at the efficiency calibration of LaBr3(Ce) and NaI(Tl) scintillation detectors using MCNPX for various types of nuclear investigations

A critical evaluation on nuclear safety properties of novel cadmium oxide-rich glass containers for transportation and waste management: Benchmarking with a reinforced concrete container

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