Fast and Thermal Neutron Removal Cross-Section for Ceramic Glass Aluminum Oxynitride DOI Open Access
A. Yıldırım

Black Sea Journal of Engineering and Science, Год журнала: 2024, Номер 7(5), С. 1022 - 1030

Опубликована: Сен. 8, 2024

This study investigates the effectiveness of transparent aluminum oxynitride (AlON) in neutron shielding, focusing on both fast and thermal neutrons. Using conventional radiation attenuation parameters, macroscopic removal cross-sections AlON were calculated for varying energies material thicknesses. The Geant4 simulation toolkit was employed to model analyze interactions with AlON. results indicate that exhibits a high shielding capacity neutrons (2 MeV), transmission factor values ranging from 0.783 0.260 thicknesses between 1 10 cm. These are nearly identical those water, which range 0.782 0.257, highlighting AlON's comparable performance. However, neutrons, performance less effective, only surpassing lead but not concrete or water. findings suggest while is highly effective it may require complementary materials adequately shield could involve using combination other create more comprehensive solution. shows significant potential as material, particularly Its integration additional enhance its overall effectiveness, making suitable various nuclear protection applications.

Язык: Английский

Synthesis, strength, microstructural and neutron/gamma attenuation properties of Al2O3-B2O3-ZnO-PbO ceramics for radiation shielding applications DOI
M.S. Al-Buriahi,

Marzoqa M. Alnairi,

Mine Kirkbinar

и другие.

Ceramics International, Год журнала: 2025, Номер unknown

Опубликована: Апрель 1, 2025

Язык: Английский

Процитировано

0

Thermal neutrons-gamma rays dual-function glass shield of boron-tungsten-reinforced borosilicate glass DOI

Dalal Abdullah Aloraini,

Aly Saeed

Materials Research Bulletin, Год журнала: 2025, Номер unknown, С. 113606 - 113606

Опубликована: Июнь 1, 2025

Язык: Английский

Процитировано

0

From Textile and Mine Waste Into Sustainable, Low‐Cost and Valuable Nanotextile Fabric‐Based Composites Through Electrospinning Technique DOI

Bahaa S. Metwally,

Najla F. Gumaah,

Saedah R. Al‐Mhyawi

и другие.

Polymers for Advanced Technologies, Год журнала: 2024, Номер 35(11)

Опубликована: Ноя. 1, 2024

ABSTRACT The rapid expansion of textile industries has contributed significantly to non‐biodegradable waste generation, presenting a global environmental challenge. Additionally, from the mining industry, such as chrysotile serpentine, contributes this issue. Therefore, study investigates possibility recycling polyamide 6 combined with serpentine produce nanotextile fabric‐based composite (NTF‐BC). This highlights significance sustainable techniques in management specifically within industry. was intensively pulverized into nanoscale particles eliminate its hazardous fibrous nature and facilitate electrospinning process. Comprehensive characterization conducted using various analytical including XRD, XRF, FT‐IR, SEM, BET, DMA, explore properties prepared fabrics function parameters (Ctl.Sp concentration, spinning distance, applied voltage, flow rate.). SEM analysis indicated optimal fabrication conditions for smoother more homogeneous NTF‐BC at Ctl.Sp concentration 7.5%, voltage 20 kV, distance 15 cm, rate 1 mL/h. XRD FT‐IR analyses showed that increasing ratio, negatively affected sample crystallinity favored α‐form over γ‐form. In terms DMA characteristics, ratio positively impacted E ′ values, minimal influence rate. Notably, highest geometric (i.e., S BET V t ) fabricated were attained lowest 5%.

Язык: Английский

Процитировано

2

Fast and Thermal Neutron Removal Cross-Section for Ceramic Glass Aluminum Oxynitride DOI Open Access
A. Yıldırım

Black Sea Journal of Engineering and Science, Год журнала: 2024, Номер 7(5), С. 1022 - 1030

Опубликована: Сен. 8, 2024

This study investigates the effectiveness of transparent aluminum oxynitride (AlON) in neutron shielding, focusing on both fast and thermal neutrons. Using conventional radiation attenuation parameters, macroscopic removal cross-sections AlON were calculated for varying energies material thicknesses. The Geant4 simulation toolkit was employed to model analyze interactions with AlON. results indicate that exhibits a high shielding capacity neutrons (2 MeV), transmission factor values ranging from 0.783 0.260 thicknesses between 1 10 cm. These are nearly identical those water, which range 0.782 0.257, highlighting AlON's comparable performance. However, neutrons, performance less effective, only surpassing lead but not concrete or water. findings suggest while is highly effective it may require complementary materials adequately shield could involve using combination other create more comprehensive solution. shows significant potential as material, particularly Its integration additional enhance its overall effectiveness, making suitable various nuclear protection applications.

Язык: Английский

Процитировано

0