Comparison of Neutron Attenuation in Graphene Hybrid Materials

Graphene is a relatively new and exciting carbon allotrope because of its exceptional property profile. While graphene currently attracts considerable research attention due to its high electron mobility, high strength, and other surprising properties, it has not yet been investigated for its radiation shielding and absorption capabilities [1,2]. Due to the comparable size of carbon atoms and neutrons, graphene-based structures are promising as effective materials for neutron shielding applications in the nuclear industry [3]. Shielding and absorption materials are critical in a variety of nuclear applications for dose reduction during the passive cooling of the nuclear fuel. Advances in the development of these materials may lead to improved characteristics, such as higher absorption and scattering rates and improved thermal performance at low density for weight-limited applications.The purpose of this study was to explore, evaluate, and compare the neutron attenuation capabilities of graphene oxide to reduced graphene oxide, the neutron attenuation of carbon nanotubes to carbon nanofibers, and different graphene oxide reduction methods. Our hypothesis is that the interfaces that these materials form at several length scales when freeze-cast into porous structures contribute to an improved neutron attenuation performance. Both the low density and high thermal stability of freeze-cast carbon structures are important and advantageous for a range of applications, making these graphene-based materials particularly attractive as possible candidates for advancements in storing and transporting spent nuclear fuel and radioactive waste.