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H.o. Tekin - One of the best experts on this subject based on the ideXlab platform.
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the impact of cr2o3 additive on Nuclear Radiation shielding properties of lif sro b2o3 glass system
Materials Chemistry and Physics, 2020Co-Authors: G Susoy, O. Kilicoglu, E Altunsoy E Guclu, M Kamislioglu, M S Alburiahi, Mohamed M Abuzaid, H.o. TekinAbstract:Abstract This study aimed to investigate the shielding performance of SrO-LiF-B2O3 glasses glass system for Nuclear security applications. The MCNPX code (version 2.6.0) and GEANT4 are used to determine the shielding parameters and the dependence with the composition of each glass, as well as the influence of Cr2O3 additive. A wide-range of Nuclear Radiation shielding investigation for gamma-ray, proton particles, fast neutrons have been studied for five different types of glasses. The calculated values for mass attenuation coefficients (μm) were utilized to determine other vital shielding properties against gamma-ray Radiation. Furthermore, some of the investigated parameters have been determined by using SRIM code and special calculation methods such as G-P fitting parameters for EBF and EABF calculation. The results showed that C25 glass with the highest Cr2O3 additive had a satisfactory capacity in Nuclear Radiation shielding.
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Physical, thermal, optical, structural and Nuclear Radiation shielding properties of Sm2O3 reinforced borotellurite glasses
Ceramics International, 2020Co-Authors: Gokhan Kilic, Shams A.m. Issa, Erkan Ilik, O. Kilicoglu, U. Gokhan Issever, Raouf El-mallawany, Bashar Issa, H.o. TekinAbstract:Abstract To observe direct effect of samarium (III) oxide reinforcement on physical, thermal, optical, structural and Nuclear Radiation attenuation properties, a broad-range experimental and numerical investigations were performed with a group of novel borotellurite glasses. FTIR spectra of powdered samples were taken at 250-4000 cm-1. The transmittance and absorption characteristics, optical band gaps, and Urbach energies were measured. The glass transition temperatures, crystallization temperatures and melting temperature values of the samples were determined. Nuclear Radiation shielding properties have been determined for gamma-ray, neutrons and heavy charged particles. The lowest transmittance and highest absorbance were reported for the TBVS1.5 sample with highest Sm2O3 additive. In addition, obtained results from the Nuclear Radiation shielding calculations have showed that TBVS1.5 sample has superior Nuclear Radiation shielding properties against gamma-ray, neutron and heavy charged particles. The increasing Sm2O3 additive has visibly improved the Nuclear Radiation attenuation properties by keeping other material properties within usable limits.
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synthesis and Nuclear Radiation shielding characterization of newly developed germanium oxide and bismuth oxide glasses
Ceramics International, 2019Co-Authors: H.o. Tekin, Shams A.m. Issa, E Altunsoy E Guclu, L R P Kassab, C D S Bordon, G R Da Silva Mattos, O. KilicogluAbstract:Abstract We present the synthesis and Nuclear Radiation shielding characterization of glasses based on germanium and bismuth oxide prepared with the melt-quenching technique. The glasses were produced using six different compositions as follows (in wt%): 40.0GeO2-60.0PbO, 38.0GeO2-62.0Bi2O3, 31.344GeO2-41.900Bi2O3-26.756PbO, 33.334GeO2-33.333TeO2-33.333PbO, 20.6GeO2-41.9TeO2-17.4Nb2O5-20.1BaO, 41.98Bi2O3-48.26PbO-8.10Ga2O3-1.66BaO. Monte Carlo method (MCNPX code, v-2.6.0) has been utilized for the determination of mass attenuation coefficients (μ/ρ) of the synthesised six different glasses. The acquired mass attenuation coefficients (μ/ρ) have been used to determine the vital parameters for gamma-ray shielding namely half value layer (HVL), mean free path (MFP), tenth value layer (TVL), effective atomic number (Zeff), exposure buildup factor (EBF), energy absorption buildup factor (EABF), transmission factors (TF), respectively. Simultaneously, effective removal cross section (∑R) values for fast neutrons and Proton mass stopping power & proton projected range have been also calculated. The results showed that among all the investigated glasses, 41.98Bi2O3-48.26PbO-8.10Ga2O3-1.66BaO glass sample has the extra capability to reduce Nuclear Radiation as a shielding material.
S.e. Wouters - One of the best experts on this subject based on the ideXlab platform.
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Spatial resolution of a diffusion-based silicon Nuclear Radiation detector
Sensors and Actuators A: Physical, 1992Co-Authors: S.e. Wouters, T. OtaredianAbstract:Abstract The spatial resolution of a diffusion-based silicon Nuclear Radiation detector is investigated by analyzing the diffusion process in both vertical and lateral directions. A theoretical model is derived, which is verified by illuminating the detector from the backside with a small light bundle. The model and the measurements show good agreement and it is demonstrated that the spatial resolution mainly depends on the Nuclear Radiation type. For ionizing particles the spatial resolution is below 1 μm and is independent of the detector thickness. For high-energy photons the resolution depends on the absorption depth and was 310 μm for the experimental device. Although the spatial resolution for X- and γ-Radiation is rather low, the diffusion-based Nuclear Radiation detector has an excellent position resolution for Nuclear particle Radiation.
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Optimization of efficiency and response time of diffusion-based Nuclear Radiation detectors
TRANSDUCERS '91: 1991 International Conference on Solid-State Sensors and Actuators. Digest of Technical Papers, 1991Co-Authors: S.e. Wouters, T. Otaredian, E M SchooneveldAbstract:The charge collection process in a diffusion-based silicon Nuclear Radiation detector was investigated by illuminating the detector at the backside with optical Radiation. The results are compared to calculations and show good agreement. The collection mechanism is characterized, and the detector response to Nuclear Radiation and its optimum with respect to efficiency and response time are calculated. Efficiency and response time are improved by reducing the detector thickness. The lower limit of detector thickness is set by the noise level and varies for different measurement systems and applications. It is concluded that a diffusion-based Nuclear Radiation detector is not inherently slow and inefficient after its performance has been optimized by selecting the right detector thickness.
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A novel diffusion-based silicon Nuclear Radiation detector
Sensors and Actuators A-physical, 1991Co-Authors: S.e. Wouters, T. Otaredian, E M SchooneveldAbstract:Abstract This paper presents a new type of silicon Nuclear' Radiation detector, in which the collection of generated charge carriers is established by means of diffusion instead of drift. This results in the omission of high-ohmic silicon, in a large reduction in bias voltage and in a very simple fabrication process. Calculations and experimental results demonstrate that different kinds of Nuclear Radiation can be detected and that a certain energy resolution can be obtained in particle measurement. The diffusion-based silicon Nuclear Radiation detector is well suited for counting applications, imaging and also, in the case of particles, for calorimetric measurements.
T. Otaredian - One of the best experts on this subject based on the ideXlab platform.
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Spatial resolution of a diffusion-based silicon Nuclear Radiation detector
Sensors and Actuators A: Physical, 1992Co-Authors: S.e. Wouters, T. OtaredianAbstract:Abstract The spatial resolution of a diffusion-based silicon Nuclear Radiation detector is investigated by analyzing the diffusion process in both vertical and lateral directions. A theoretical model is derived, which is verified by illuminating the detector from the backside with a small light bundle. The model and the measurements show good agreement and it is demonstrated that the spatial resolution mainly depends on the Nuclear Radiation type. For ionizing particles the spatial resolution is below 1 μm and is independent of the detector thickness. For high-energy photons the resolution depends on the absorption depth and was 310 μm for the experimental device. Although the spatial resolution for X- and γ-Radiation is rather low, the diffusion-based Nuclear Radiation detector has an excellent position resolution for Nuclear particle Radiation.
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Optimization of efficiency and response time of diffusion-based Nuclear Radiation detectors
TRANSDUCERS '91: 1991 International Conference on Solid-State Sensors and Actuators. Digest of Technical Papers, 1991Co-Authors: S.e. Wouters, T. Otaredian, E M SchooneveldAbstract:The charge collection process in a diffusion-based silicon Nuclear Radiation detector was investigated by illuminating the detector at the backside with optical Radiation. The results are compared to calculations and show good agreement. The collection mechanism is characterized, and the detector response to Nuclear Radiation and its optimum with respect to efficiency and response time are calculated. Efficiency and response time are improved by reducing the detector thickness. The lower limit of detector thickness is set by the noise level and varies for different measurement systems and applications. It is concluded that a diffusion-based Nuclear Radiation detector is not inherently slow and inefficient after its performance has been optimized by selecting the right detector thickness.
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A novel diffusion-based silicon Nuclear Radiation detector
Sensors and Actuators A-physical, 1991Co-Authors: S.e. Wouters, T. Otaredian, E M SchooneveldAbstract:Abstract This paper presents a new type of silicon Nuclear' Radiation detector, in which the collection of generated charge carriers is established by means of diffusion instead of drift. This results in the omission of high-ohmic silicon, in a large reduction in bias voltage and in a very simple fabrication process. Calculations and experimental results demonstrate that different kinds of Nuclear Radiation can be detected and that a certain energy resolution can be obtained in particle measurement. The diffusion-based silicon Nuclear Radiation detector is well suited for counting applications, imaging and also, in the case of particles, for calorimetric measurements.
O. Kilicoglu - One of the best experts on this subject based on the ideXlab platform.
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the impact of cr2o3 additive on Nuclear Radiation shielding properties of lif sro b2o3 glass system
Materials Chemistry and Physics, 2020Co-Authors: G Susoy, O. Kilicoglu, E Altunsoy E Guclu, M Kamislioglu, M S Alburiahi, Mohamed M Abuzaid, H.o. TekinAbstract:Abstract This study aimed to investigate the shielding performance of SrO-LiF-B2O3 glasses glass system for Nuclear security applications. The MCNPX code (version 2.6.0) and GEANT4 are used to determine the shielding parameters and the dependence with the composition of each glass, as well as the influence of Cr2O3 additive. A wide-range of Nuclear Radiation shielding investigation for gamma-ray, proton particles, fast neutrons have been studied for five different types of glasses. The calculated values for mass attenuation coefficients (μm) were utilized to determine other vital shielding properties against gamma-ray Radiation. Furthermore, some of the investigated parameters have been determined by using SRIM code and special calculation methods such as G-P fitting parameters for EBF and EABF calculation. The results showed that C25 glass with the highest Cr2O3 additive had a satisfactory capacity in Nuclear Radiation shielding.
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Physical, thermal, optical, structural and Nuclear Radiation shielding properties of Sm2O3 reinforced borotellurite glasses
Ceramics International, 2020Co-Authors: Gokhan Kilic, Shams A.m. Issa, Erkan Ilik, O. Kilicoglu, U. Gokhan Issever, Raouf El-mallawany, Bashar Issa, H.o. TekinAbstract:Abstract To observe direct effect of samarium (III) oxide reinforcement on physical, thermal, optical, structural and Nuclear Radiation attenuation properties, a broad-range experimental and numerical investigations were performed with a group of novel borotellurite glasses. FTIR spectra of powdered samples were taken at 250-4000 cm-1. The transmittance and absorption characteristics, optical band gaps, and Urbach energies were measured. The glass transition temperatures, crystallization temperatures and melting temperature values of the samples were determined. Nuclear Radiation shielding properties have been determined for gamma-ray, neutrons and heavy charged particles. The lowest transmittance and highest absorbance were reported for the TBVS1.5 sample with highest Sm2O3 additive. In addition, obtained results from the Nuclear Radiation shielding calculations have showed that TBVS1.5 sample has superior Nuclear Radiation shielding properties against gamma-ray, neutron and heavy charged particles. The increasing Sm2O3 additive has visibly improved the Nuclear Radiation attenuation properties by keeping other material properties within usable limits.
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synthesis and Nuclear Radiation shielding characterization of newly developed germanium oxide and bismuth oxide glasses
Ceramics International, 2019Co-Authors: H.o. Tekin, Shams A.m. Issa, E Altunsoy E Guclu, L R P Kassab, C D S Bordon, G R Da Silva Mattos, O. KilicogluAbstract:Abstract We present the synthesis and Nuclear Radiation shielding characterization of glasses based on germanium and bismuth oxide prepared with the melt-quenching technique. The glasses were produced using six different compositions as follows (in wt%): 40.0GeO2-60.0PbO, 38.0GeO2-62.0Bi2O3, 31.344GeO2-41.900Bi2O3-26.756PbO, 33.334GeO2-33.333TeO2-33.333PbO, 20.6GeO2-41.9TeO2-17.4Nb2O5-20.1BaO, 41.98Bi2O3-48.26PbO-8.10Ga2O3-1.66BaO. Monte Carlo method (MCNPX code, v-2.6.0) has been utilized for the determination of mass attenuation coefficients (μ/ρ) of the synthesised six different glasses. The acquired mass attenuation coefficients (μ/ρ) have been used to determine the vital parameters for gamma-ray shielding namely half value layer (HVL), mean free path (MFP), tenth value layer (TVL), effective atomic number (Zeff), exposure buildup factor (EBF), energy absorption buildup factor (EABF), transmission factors (TF), respectively. Simultaneously, effective removal cross section (∑R) values for fast neutrons and Proton mass stopping power & proton projected range have been also calculated. The results showed that among all the investigated glasses, 41.98Bi2O3-48.26PbO-8.10Ga2O3-1.66BaO glass sample has the extra capability to reduce Nuclear Radiation as a shielding material.
E M Schooneveld - One of the best experts on this subject based on the ideXlab platform.
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Optimization of efficiency and response time of diffusion-based Nuclear Radiation detectors
TRANSDUCERS '91: 1991 International Conference on Solid-State Sensors and Actuators. Digest of Technical Papers, 1991Co-Authors: S.e. Wouters, T. Otaredian, E M SchooneveldAbstract:The charge collection process in a diffusion-based silicon Nuclear Radiation detector was investigated by illuminating the detector at the backside with optical Radiation. The results are compared to calculations and show good agreement. The collection mechanism is characterized, and the detector response to Nuclear Radiation and its optimum with respect to efficiency and response time are calculated. Efficiency and response time are improved by reducing the detector thickness. The lower limit of detector thickness is set by the noise level and varies for different measurement systems and applications. It is concluded that a diffusion-based Nuclear Radiation detector is not inherently slow and inefficient after its performance has been optimized by selecting the right detector thickness.
-
A novel diffusion-based silicon Nuclear Radiation detector
Sensors and Actuators A-physical, 1991Co-Authors: S.e. Wouters, T. Otaredian, E M SchooneveldAbstract:Abstract This paper presents a new type of silicon Nuclear' Radiation detector, in which the collection of generated charge carriers is established by means of diffusion instead of drift. This results in the omission of high-ohmic silicon, in a large reduction in bias voltage and in a very simple fabrication process. Calculations and experimental results demonstrate that different kinds of Nuclear Radiation can be detected and that a certain energy resolution can be obtained in particle measurement. The diffusion-based silicon Nuclear Radiation detector is well suited for counting applications, imaging and also, in the case of particles, for calorimetric measurements.
