Development of Graphene-based nuclear fuel cladding for improved safety.
The project is about novel research on multilayer SiC–graphene composite material for application in reactor nuclear fuel cladding in order to improve its safety and performance. Recent studies in this area clearly indicate that ceramic cladding, specifically, composite Silicon Carbide (SiC), can effectively mitigate the problems related to different accidents and can thus be used as an accident tolerant replacement for traditional Zr-based cladding. Despite its numerous advantages as compared to Zr, SiC has one strong drawback which is related to being a ceramic material with high embrittlement level. Among many other possible alternatives such as, for example, mixed ceramic/metal cladding, cladding complemented with graphene material (due to its outstanding properties) can be considered to be a good option to improve the mechanical properties of SiC cladding. The idea is to mix graphene with the reactor cladding material to improve its properties. Graphene is an optimal material which means that you do not have to compromise. But of course, since graphene is a new material, there are still questions if it will work and how. But due to its optimal qualities, it is worth testing. I have never worked with graphene before, so it is especially exciting to do something completely new.
Victor Dykin (contact)
Forskare at Nuclear Engineering
Doktorand at Chalmers, Microtechnology and Nanoscience (MC2), Electronics Material and Systems Laboratory
at Nuclear Engineering
Associate Professor at Materials Microstructure
Project ID: 14-377
Funding Chalmers participation during 2014–2015
Related Areas of Advance and Infrastructure
Nanoscience and Nanotechnology (SO 2010-2017, EI 2018-)
Areas of Advance
Areas of Advance