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Determination of X-ray and gamma-ray shielding capabilities of recycled glass derived from deteriorated silica gel

  • P. Sopapan;O. Jaiboon;R. Laopaiboon;C. Yenchai;C. Sriwunkum;S. Issarapanacheewin;T. Akharawutchayanon;K. Yubonmhat
    • Nuclear Engineering and Technology
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    • v.55 no.9
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    • pp.3441-3449
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    • 2023
  • We determined the radiation shielding properties for 10CaO-xPbO-(90-x) deteriorated silica gel (DSG) glass system (x = 20, 25, 30, 35, 40, and 45 mol.%). The mass attenuation coefficient (MAC) has been estimated at photon energies of 74.23, 97.12, 122, 662, 1173, and 1332 keV using a narrow beam X-ray attenuation and transmission experiment, the XCOM program, and a PHITS simulation. The obtained MAC values were applied to estimate the half value layer (HVL), mean free path (MFP), effective atomic number, and effective electron density. Results show that the MAC value of the studied glasses ranges between 0.0549 and 1.4415 cm2/g, increases with the amount of PbO, and decreases with increasing photon energy. The HVL and MFP values decrease with increasing PbO content and increase with increasing photon energy. The recycled glass, with the addition of PbO content (20-45 mol.%), exhibited excellent radiation shielding capabilities compared to standard barite and ferrite concretes and some glass systems. Moreover, the experimental radiation shielding parameters agree with the XCOM and PHITS values. This study suggests that this new waste-recycled glass is an effective and cost-saving candidate for X-ray and gamma-ray shielding applications.

Physical characterization and radiation shielding features of B2O3-As2O3 glass ceramic

  • Mohamed Y. Hanfi;Ahmed K. Sakr;A.M. Ismail;Bahig M. Atia;Mohammed S. Alqahtani;K.A. Mahmoud
    • Nuclear Engineering and Technology
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    • v.55 no.1
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    • pp.278-284
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    • 2023
  • The synthetic B2O3-As2O3 glass ceramic are prepared to investigate the physical properties and the radiation shielding capabilities with the variation of concentration of the As2O3 with 10, 20, 30, and 40%, respectively. XRD analyses are performed on the fabricated glass-ceramic and depicted the improvement of crystallinity by adding As2O3. The radiation shielding properties are studied for the B2O3-As2O3 glass ceramic. The values of linear attenuation coefficient (LAC) are varied with the variation of incident photon gamma energy (23.1-103 keV). The LAC values enhanced from 12.19 cm-1-37.75 cm-1 by raising the As2O3 concentration from 10 to 40 mol% at low gamma energy (23.1 keV) for BAs10 and BAs40, respectively. Among the shielding parameters, the half-value layer, transmission factor, and radiation protection efficiency are estimated. Furthermore, the fabricated samples of glass ceramic have low manufacturing costs and good shielding features compared to the previous work. It can be concluded the B2O3-As2O3 glass ceramic is appropriate to apply in X-ray or low-energy gamma-ray shielding applications.

Investigations on borate glasses within SBC-Bx system for gamma-ray shielding applications

  • Rammah, Y.S.;Tekin, H.O.;Sriwunkum, C.;Olarinoye, I.;Alalawi, Amani;Al-Buriahi, M.S.;Nutaro, T.;Tonguc, Baris T.
    • Nuclear Engineering and Technology
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    • v.53 no.1
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    • pp.282-293
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    • 2021
  • This paper examines gamma-ray shielding properties of SBC-Bx glass system with the chemical composition of 40SiO2-10B2O3-xBaO-(45-x)CaO- yZnO- zMgO (where x = 0, 10, 20, 30, and 35 mol% and y = z = 6 mol%). Mass attenuation coefficient (µ/ρ) which is an essential parameter to study gamma-ray shielding properties was obtained in the photon energy range of 0.015-15 MeV using PHITS Monte Carlo code for the proposed glasses. The obtained results were compared with those calculated by WinXCOM program. Both the values of PHITS code and WinXCOM program were observed in very good agreement. The (µ/ρ values were then used to derive mean free path (MFP), electron density (Neff), effective atomic number (Zeff), and half value layer (HVL) for all the glasses involved. Additionally, G-P method was employed to estimate exposure buildup factor (EBF) for each glass in the energy range of 0.015-15 MeV up to penetration depths of 40 mfp. The results reveal that gamma-ray shielding effectiveness of the SBC-Bx glasses evolves with increasing BaO content in the glass sample. Such that SBC-B35 glass has superior shielding capacity against gamma-rays among the studied glasses. Gamma-ray shielding properties of SBC-B35 glass were compared with different conventional shielding materials, commercial glasses, and newly developed HMO glasse. Therefore, the investigated glasses have potential uses in gamma shielding applications.

Optical, thermal and gamma ray attenuation characteristics of tungsten oxide modified: B2O3-SrCO3-TeO2-ZnO glass series

  • Hammam Abdurabu Thabit;Abd Khamim Ismail;M.I. Sayyed;S. Hashim;I. Abdullahi;Mohamed Elsafi;K. Keshavamurthy;G. Jagannath
    • Nuclear Engineering and Technology
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    • v.56 no.1
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    • pp.247-256
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    • 2024
  • The glass series modified by tungsten oxide was created using the compounds (75-x) B2O3- 10SrCO3- 8TeO2- 7ZnO - xWO3, where x = 0, 1, 5, 10, 22, 27, 34, and 40% mole percentage. A UV-visible spectrophotometer and thermogravimetric-differential thermal analysis (TG-DTA) methods were employed to characterize the specimen's optical and phase transition attributes, respectively. The mass-attenuation coefficient (AC) of all created glasses from BSTZW0 to BSTZ7 was estimated using Geant4 code from 0.05 to 3 MeV and compared to the XCOM software results, with a relative difference of less than 2% between the two results. The increase of WO3 percentage lead to an increase in the Linear-AC at each studied energy, and this is mainly due to the fact that the higher the percentage of WO3 in the glass increases its density which causes an increase in the Linear-AC, so an energy of 0.06 MeV, as an example, the values of the Linear-AC was 4.009, 4.509, 5.442, 6812, 8.564, 9.856, 10.999 and 11.628 cm-1 form BSTZW0 too BSTZW7, respectively. The Half-VL (value layer), Mean-FP (free path), Tenth-VL, and Radiation attenuation performance (RAP) were also calculated for the current BSTZW-glass samples and revealed that BSTZW7 had the best gamma ray attenuation performance at all discussed energies when compared to other studied glass samples.

Fabrication of Er/Yb co-doped phosphate glass waveguides by potassium ion exchange (Er과 Yb이 첨가된 인산염 유리의 K 이온교환 공정을 통한 증폭용 광도파로 제조)

  • 김덕준;신장욱;박상호;김태흥;심재기;성희경
    • Korean Journal of Optics and Photonics
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    • v.11 no.3
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    • pp.202-205
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    • 2000
  • One step thermal potassium ion exchange process was carried out to form optical channel waveguides in an ErNb co-doped phosphate glass. Flowing oxygen gas into KN03 melt during ion exchange was effective to prevent glass surface damage that causes an increase of waveguide propagation loss. Amplification characteristics of the waveguides were evaluated at $1.5{\mu}m$ signal wavelength with 980 om laser diode pump. A 45 mm long waveguide whose processing parameters had been optimized exhibited a small signal net gain of 7.5 dB at the launched pump power of 160 mW.160 mW.

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Effect of the Photosensitizer on the Photo refractive Effect Using a Low $T_g$ Sol-Gel Glass

  • Choi, Dong-Hoon;Jun, Woong-Gi;Oh, Kwang-Yong;Yoon, Han-Na;Kim, Jae-Hong
    • Macromolecular Research
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    • v.11 no.4
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    • pp.250-255
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    • 2003
  • We prepared the photorefractive sol-gel glass based on organic-inorganic hybrid materials containing a charge transporting molecule, second-order nonlinear optical (NLO) chromophore, photosensitizer, and plasticizer. Carbazole and 2-{ 4-[(2-hydroxy-ethyl)-methyl-amino]-benzylidene}-malononitrile were reacted with isocyanato-triethoxy silane and the functionalized silanes were employed to fabricate the efficient photorefractive media induding 2,4,7-trinitrot1uorenone (TNF) to form a charge transfer complex. The prepared sol-gel glass samples showed a large net gain coefficient and high diffraction efficiency at a certain composition. As the concentration of photosensitizer increased, the photorefractive properties were enhanced due to an increment of charge carrier density. Dynamic behavior of the diffraction efficiency was also investigated with the concentration of the photosensitizer.

γ-Ray Shielding Behaviors of Some Nuclear Engineering Materials

  • Mann, Kulwinder Singh
    • Nuclear Engineering and Technology
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    • v.49 no.4
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    • pp.792-800
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    • 2017
  • The essential requirement of a material to be used for engineering purposes at nuclear establishments is its ability to attenuate the most penetrating ionizing radiations, gamma $({\gamma})-rays$. Mostly, high-Z materials such as heavy concrete, lead, mercury, and their mixtures or alloys have been used in the construction of nuclear establishments and thus termed as nuclear engineering materials (NEM). The NEM are classified into two categories, namely opaque and transparent, depending on their behavior towards the visible spectrum of EM waves. The majority of NEM are opaque. By contrast, various types of glass, which are transparent to visible light, are necessary at certain places in the nuclear establishments. In the present study, ${\gamma}-ray$ shielding behaviors (GSB) of six glass samples (transparent NEM) were evaluated and compared with some opaque NEM in a wide range of energy (15 keV-15 MeV) and optical thickness (OT). The study was performed by computing various ${\gamma}-ray$ shielding parameters (GSP) such as the mass attenuation coefficient, equivalent atomic number, and buildup factor. A self-designed and validated computer-program, the buildup factor-tool, was used for various computations. It has been established that some glass samples show good GSB, thus can safely be used in the construction of nuclear establishments in conjunction with the opaque NEM as well.

Determination of reaction kinetics during vitrification of radioactive liquid waste for different types of base glass

  • Suneel, G.;Rajasekaran, S.;Selvakumar, J.;Kaushik, Chetan P.;Gayen, J.K.;Ravi, K.V.
    • Nuclear Engineering and Technology
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    • v.51 no.3
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    • pp.746-754
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    • 2019
  • Vitrification of radioactive liquid waste (RLW) provides a feasible solution for isolating radionuclides from the biosphere for an extended period. In vitrification, base glass and radioactive waste are added simultaneously into the melter. Determination of heat and mass transfer rates is necessary for rational design and sizing of melter. For obtaining an assured product quality, knowledge of reaction kinetics associated with the thermal decomposition of waste constituents is essential. In this study Thermogravimetry (TG) - Differential Thermogravimetry (DTG) of eight kinds of nitrates and two oxides, which are major components of RLW, is investigated in the temperature range of 298-1273 K in the presence of base glasses of five component (5C) and seven component (7C). Studies on thermal behavior of constituents in RLW were carried out at heating rates ranging from 10 to $40\;K\;min^{-1}$ using TG - DTG. Thermal behavior and related kinetic parameters of waste constituents, in the presence of 5C and 7C base glass compositions were also investigated. The activation energy, pre-exponential factor and order of the reaction for the thermal decomposition of 24% waste oxide loaded glasses were estimated using Kissinger method.

Thermally assisted IRSL and VSL measurements of display glass from mobile phones for retrospective dosimetry

  • Discher, Michael;Kim, Hyoungtaek;Lee, Jungil
    • Nuclear Engineering and Technology
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    • v.54 no.2
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    • pp.429-436
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    • 2022
  • Investigations of retrospective dosimetry have shown that components of mobile phones are suitable as emergency dosimeters in case of radiological incidents. For physical dosimetry, components can be read out using optically stimulated luminescence (OSL), thermoluminescence (TL) and phototransferred thermoluminescence (PTTL) methods to determine the absorbed dose. This paper deals with a feasibility study of display glass from modern mobile phones that are measured by thermally assisted (Ta) optically stimulated luminescence. Violet (VSL, 405 nm) and infrared (IRSL, 850 nm) LEDs were used for optical stimulation and two protocols (Ta-VSL and Ta-IRSL) were tested. The aim was to systematically investigate the luminescence properties, compare the results to blue stimulated Ta-BSL protocol (458 nm) and to develop a robust measurement protocol for the usage as an emergency dosimeter after an incident with ionizing radiation. First, the native signals were measured to calculate the zero dose signal. Next, the reproducibility and dose response of the luminescence signals were analyzed. Finally, the signal stability was tested after the storage of irradiated samples at room temperature. In general, the developed Ta-IRSL and Ta-VSL protocols indicate usability, however, further research is needed to test the potential of a new protocol for physical retrospective dosimetry.

Enhancement of nuclear radiation shielding and mechanical properties of YBiBO3 glasses using La2O3

  • Issa, Shams A.M.;Ali, Atif Mossad;Tekin, H.O.;Saddeek, Y.B.;Al-Hajry, Ali;Algarni, Hamed;Susoy, G.
    • Nuclear Engineering and Technology
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    • v.52 no.6
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    • pp.1297-1303
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    • 2020
  • In this study, nuclear radiation shielding and rigidity parameters of Y (0.1-x)B0.6Bi1.8O3La2x glassy system were investigated in order to determine it's suitability for use as nuclear radiation shielding materials. Therefore, a group of bismuth borate glass samples with La2O3 additive were synthesized using the technique of melt quenching. According to the results, the increase of the La2O3 additive increases the density of the glass samples and the mass attenuation coefficient (μm) values, whereas the half-value layer (HVL) and mean free path (MFP) values decrease. The effective atomic number (Zeff) is also enhanced with an increment of both mass removal cross section for neutron (ΣR) and absorption neutron scattering cross section (σabs). In addition to the other parameters, rigidity parameter values were theoretically examined. The increase of La2O3 causes some other important magnitudes to increase. These are the average crosslink density, the number of bonds per unit volume, as well as the stretching force constant values of these glass samples. These results are in concordance with the increase of elastic moduli in terms of the Makishima-Mackenzie model. This model showed an increase in the rigidity of the glass samples as a function of La2O3.