Optimizing gamma-ray shielding for boron neutron capture therapy by using unglazed ceramic composites

Ali, M.S.; Hassan, G.S.; Shoraiet, G.M.; Abdelmonem, A.M.

doi:10.1016/j.nimb.2024.165450

Nuclear Instruments and Methods in Physics Research Section B:

2024

DOI: 10.1016/j.nimb.2024.165450

|View full text |Cite

Optimizing gamma-ray shielding for boron neutron capture therapy by using unglazed ceramic composites

M.S. Ali,

G.S. Hassan,

G.M. Shoraiet

et al.

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...

Citation Types

Supporting

Mentioning

Contrasting

Year Published

2024

2025

Publication Types

Select...

Article2

Relationship

Self Cite0

Independent2

Authors

Journals

Cited by 2 publications

References 33 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

Radiation-thermal modification of fluoroplastic composite and evaluation of its radiation-protective characteristics

Pavlenko,

Kashibadze,

Noskov

et al. 2025

Materials Chemistry and Physics

View full text Add to dashboard Cite

Radiation-thermal modification of fluoroplastic composite and evaluation of its radiation-protective characteristics

Pavlenko,

Kashibadze,

Noskov

et al. 2025

Materials Chemistry and Physics

View full text Add to dashboard Cite

Fast and Thermal Neutron Removal Cross-Section for Ceramic Glass Aluminum Oxynitride

Yıldırım

2024

Black Sea Journal of Engineering and Science

View full text Add to dashboard Cite

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

show abstract

scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.

Contact Info

customersupport@researchsolutions.com

10624 S. Eastern Ave., Ste. A-614

Henderson, NV 89052, USA

This site is protected by reCAPTCHA and the Google Privacy Policy and Terms of Service apply.

Blog Terms and Conditions API Terms Privacy Policy Contact Cookie Preferences Do Not Sell or Share My Personal Information

Made with 💙 for researchers

Part of the Research Solutions Family.

Optimizing gamma-ray shielding for boron neutron capture therapy by using unglazed ceramic composites

Cited by 2 publications

References 33 publications

Radiation-thermal modification of fluoroplastic composite and evaluation of its radiation-protective characteristics

Radiation-thermal modification of fluoroplastic composite and evaluation of its radiation-protective characteristics

Fast and Thermal Neutron Removal Cross-Section for Ceramic Glass Aluminum Oxynitride

Contact Info

Product

Resources

About