Potential Radiation-Shielding Materials for Nuclear Waste Management

Effective radiation shielding is a cornerstone of nuclear waste management, ensuring the safe containment and isolation of radioactive materials. Advances in material science have introduced innovative glass-based materials and ceramic-concrete hybrids, offering superior radiation protection and addressing the structural and environmental challenges inherent in nuclear waste storage. These advancements enhance the safety and sustainability of managing radioactive waste and safeguarding human health and the environment. Asst. Prof. Duygu Şen Baykal from the Faculty of Engineering and Architecture at Nişantaşı University, as a member of a team investigating the roles of advanced glass materials in radiation protection, conducts extensive studies on the potential applications and unique characteristics of these materials.

Oxide-reinforced Glass

Oxide-reinforced glasses are strong contenders in radiation shielding due to their transparency, chemical stability, and adaptability. Glasses reinforced with oxides can outperform certain composite materials in gamma-ray shielding, with the potential for further improvement through optimization of oxide content. Glasses enriched with certain oxides enhance gamma-ray attenuation by increasing density and incorporating heavy elements, while maintaining the importance of other compounds for neutron shielding. Glasses with high-density components and excellent photon interaction offer superior shielding efficiency, making them ideal for medical, nuclear, and radiation-sensitive environments [123].

Ceramic-concrete Composites

Ceramic-concrete hybrids combine concrete’s versatility with the radiation attenuation of heavy metal oxides like iron and barium, enhancing photon attenuation through higher density and atomic numbers. Their customizable, high-density structures offer cost-effective, efficient shielding against gamma rays and neutrons for nuclear, medical, and aerospace applications [4].

Innovative materials such as glass-based systems and ceramic-concrete hybrids represent significant progress in radiation shielding for nuclear waste management. By harnessing advances in material science and computational modeling, these technologies pave the way for safer, more sustainable solutions for storing and containing nuclear waste.

*Notes: This article provides research teasers for each reference to showcase the novelties

References

[1] ALMisned, G., Sen Baykal, D., Elshami, W., Susoy, G., Kilic, G., & Tekin, H. O. (2024). A comparative analysis of shielding effectiveness in glass and concrete containers. Open Physics, 22(1), 20240019. https://doi.org/10.1515/phys-2024-0019

[2] ALMisned, G., Sen Baykal, D., Ilik, E., Kilic, G., & Tekin, H. O. (2023). The role of ZrO2 as glass-network former on radiation transmission properties of aluminoborosilicate (Abs) glasses: A glass type for nuclear waste immobilization. Ceramics International, 49(23), 39124–39133. https://doi.org/10.1016/j.ceramint.2023.09.252

[3] Sen Baykal, D., Afaneh, F., Susoy, G., Al-Omari, S., ALMisned, G., Kilic, G., Khattari, Z. Y., Issa, B., & Tekin, H. O. (2024). Enhancing mechanical, physical, radiation attenuation properties in alumino-barium-titanium-calcium-lithium glasses for nuclear applications: The pivotal role of TiO additives. Radiation Physics and Chemistry, 217, 111507. https://doi.org/10.1016/j.radphyschem.2023.111507

[4] AlMisned, G., Susoy, G., Sen Baykal, D., Kilic, G., & Tekin, H. O. (2024). An extensive benchmark analysis of advanced ceramic-concretes towards strategic material selection for nuclear applications and waste management. Ceramics International, 50(10), 17075–17085. https://doi.org/10.1016/j.ceramint.2024.02.184

Potential Radiation-Shielding Materials for Nuclear Waste Management

Effective radiation shielding is a cornerstone of nuclear waste management, ensuring the safe containment and isolation of radioactive materials. Advances in material science have introduced innovative glass-based materials and ceramic-concrete hybrids, offering superior radiation protection and addressing the structural and environmental challenges inherent in nuclear waste storage. These advancements enhance the safety and sustainability of managing radioactive waste and safeguarding human health and the environment. Asst. Prof. Duygu Şen Baykal from the Faculty of Engineering and Architecture at Nişantaşı University, as a member of a team investigating the roles of advanced glass materials in radiation protection, conducts extensive studies on the potential applications and unique characteristics of these materials.

Oxide-reinforced Glass

Oxide-reinforced glasses are strong contenders in radiation shielding due to their transparency, chemical stability, and adaptability. Glasses reinforced with oxides can outperform certain composite materials in gamma-ray shielding, with the potential for further improvement through optimization of oxide content. Glasses enriched with certain oxides enhance gamma-ray attenuation by increasing density and incorporating heavy elements, while maintaining the importance of other compounds for neutron shielding. Glasses with high-density components and excellent photon interaction offer superior shielding efficiency, making them ideal for medical, nuclear, and radiation-sensitive environments [123].

Ceramic-concrete Composites

Ceramic-concrete hybrids combine concrete’s versatility with the radiation attenuation of heavy metal oxides like iron and barium, enhancing photon attenuation through higher density and atomic numbers. Their customizable, high-density structures offer cost-effective, efficient shielding against gamma rays and neutrons for nuclear, medical, and aerospace applications [4].

Innovative materials such as glass-based systems and ceramic-concrete hybrids represent significant progress in radiation shielding for nuclear waste management. By harnessing advances in material science and computational modeling, these technologies pave the way for safer, more sustainable solutions for storing and containing nuclear waste.

*Notes: This article provides research teasers for each reference to showcase the novelties

References

[1] ALMisned, G., Sen Baykal, D., Elshami, W., Susoy, G., Kilic, G., & Tekin, H. O. (2024). A comparative analysis of shielding effectiveness in glass and concrete containers. Open Physics, 22(1), 20240019. https://doi.org/10.1515/phys-2024-0019

[2] ALMisned, G., Sen Baykal, D., Ilik, E., Kilic, G., & Tekin, H. O. (2023). The role of ZrO2 as glass-network former on radiation transmission properties of aluminoborosilicate (Abs) glasses: A glass type for nuclear waste immobilization. Ceramics International, 49(23), 39124–39133. https://doi.org/10.1016/j.ceramint.2023.09.252

[3] Sen Baykal, D., Afaneh, F., Susoy, G., Al-Omari, S., ALMisned, G., Kilic, G., Khattari, Z. Y., Issa, B., & Tekin, H. O. (2024). Enhancing mechanical, physical, radiation attenuation properties in alumino-barium-titanium-calcium-lithium glasses for nuclear applications: The pivotal role of TiO additives. Radiation Physics and Chemistry, 217, 111507. https://doi.org/10.1016/j.radphyschem.2023.111507

[4] AlMisned, G., Susoy, G., Sen Baykal, D., Kilic, G., & Tekin, H. O. (2024). An extensive benchmark analysis of advanced ceramic-concretes towards strategic material selection for nuclear applications and waste management. Ceramics International, 50(10), 17075–17085. https://doi.org/10.1016/j.ceramint.2024.02.184