Speaker
Description
Graphite composite comprising of 64 wt% of natural graphite, 16 wt% of synthetic graphite and 20 wt% of phenolic resin binder heat treated at 1800 0C have been used to encapsulate the TRISO coated fuel particles in the PBMR and considered to serve in the initial state of neutron moderation as well as heat conduction. The structural and thermal properties of the pristine and irradiated samples will be compared to IG110 nuclear graphite so as to check its degree of applicability in the nuclear reactor. The structure and disorder of both materials is investigated using X-ray diffraction (XRD) and Raman spectroscopy, while Low and high temperature thermal and electrical properties is investigated using physical property measuring system (PPMS) and laser flash analyser (LFA) respectively.
| Consider for a student <br> award (Yes / No)? | Yes |
|---|---|
| Level (Hons, MSc, <br> PhD, other)? | Msc |
| Would you like to <br> submit a short paper <br> for the Conference <br> Proceedings (Yes / No)? | No |
